ML061730173
| ML061730173 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 08/20/1992 |
| From: | Marx D Vermont Yankee |
| To: | Kooiker B NRC Region 1, State of VT, Agency of Natural Resources |
| References | |
| %dam200611 | |
| Download: ML061730173 (72) | |
Text
tfZ August 20, 1992 Mr. Brian Kooiker Permits, Compliance, and Protection Departn~ent of Environmental Conservation Agency of Natural Resources State of Vermont 103 South Main Street-The Annex Waterbury, VT 05671-0405
Subject:
NPDES unplanned discharge, August 14, 1992.
Reference:
NPDES Permit No. 3-1199, VT0000264.
Dear Mr. Kooiker:
This letter is written to document an incident which occurred at the Vermont Yankee Nuclear Power Station on August 14, 1992 which resulted in an unplanned release to the Connecticut River at Vernon of a limited amount of water slightly contaminated with radionuclides.
The incident was verbally reported to Ms Nancy Manley of the Agency on August 18th at 8:30 a.m. and earlier to Mr William Sherman, Vermont State Nuclear Engineer, on August 17th at 10:00 a.m.
A description of the event is attached. The incident is still under evaluation by Vermont Yankee personnel and will result in a Corrective Action Report.
Current radiological analyses show that limits established by the Nuclear Regulatory Commission have not been exceeded. The event will be reported in the semiannual Radiological Effluent Report.
In the event you should require further information, please do not hesitate to call.
Sincerely, Daniel J. Marx, Ph.D.
Environmental Scientist Attachment, VYNPC, 8/20/92.
Attachment, VYNPC, 8/20/92 Overflow of Condensate Demineralizer Backwash Receiving Tank On August 14, 1992 at approximately 1330, while backwashing the B condensate demineralizer and transferring the contents to the condensate demineralizer backwash tank, the electric pump which transfers the water from the tank to radwaste failed, resulting in the backwash receiving tank overflowing onto the floor. The water was radioactively contaminated and contained some resin material. The floor in the vicinity of the tank was flooded to a depth of approximately 1-2 inches.'%
Samples" taken in a nearby sump indicated the presence of radioactive Iodine and Tritium.
The sump pumps are designed to cycle if required by level so it is possible that some contaminated water was discharged to the river by way of the service water system (10,000 gpm) and then into the main circulating water system (360,000 gpm) before entering the Connecticut River.
The precise volume of contaminated water that may have been discharged to the river is estimated to be less than 15 gallons. Radiation monitors and samples at the point of discharge did not record any evidence of radioactivity and remained normal during the entire event.
Vermont Yankee personnel isolated the sump pumps and terminated the potential discharge at approximately 1430.
Based on radiological analysis of samples taken from the floor, sumps, and the discharge structure, and assuming bounding conditions, Vermont Yankee calculated that Technical Specifications and NRC 10CFR requirements and limits were not exceeded and the event was not reportable to the NRC. The calculated parameter values were also below Vermont Department of Health Radiological Health limits and the NPDES Permit limits.
The calculated values were based on the extremely conservative assumption that radioactive water was pumped out of the sumps and discharged through the normal flow path to the river continuously during the event. The calculation assumes dilution by the flow of the circulating water system (360,000 gpm) occurring concurrently with the discharge.
The actual volume of radioactive water discharged is estimated to be three orders of magnitude below the bounding calculated values, or less than 15 gallons. Connecticut River flow at the time of the incident was approximately 6000 cfs.
DJM.8/20/92
SUMMARY
OF APPLICABLE LIMITS AND "JUSTIFIABLE" CALCULATED VALUES FOR LIQUID RELEASE OF 8/14/92 Bases -
The "Calculated Value is based upon ithe assumption that 1000 gallons of radioactive water was pumped out of the TB Clean Sump and discharged, through the normal flow path,.to the riVer.
The calculation assumes dilution by the flow of Circulating Water(360000 gpm) Occurring concurrently with this discharge..
APPLICABLE LIMITS TECHNICAL SPECIFICATIONS LIQUID 'RELEASE CalculatedValue
-Liquid Effluents: Concentrations 1)T.S.3.8.A.1 I 1 MPC as determined by 10CFR20, App.B, Table II, Col. 2 conc.(Noble Gases excluded) 2)T.S.3.8.A.I -
Total'Noble Gases:.
Conc.
< 2E-4 uci/cc Liquid Effluents: Dose.
I)Total Body Dose.-T.S.3.8.B.*
1.5.mrem in any-quarter, 3 mrem total for year...
2)Organ Dose -. T.S.3.8.B.1:-..
'5 mrem in any quarter, 10 mrem total for year 10CFR50.72 REPORTING REQUIREMENTS 2 times MPC when aVeraged.over one hour NPDES REPORTING REQUIREMENTS.
Unplanned Releases 10CFR20 App B, Table II, Col.2 (1
MPC)
- Total Radionuclides(excluding tritium) shall be K 5 curies per year Total Tritium shall be K 5 curies per year Dose Calendar quarter -
- 1.5 mrem total body 5 mrem to any organ Calendar year S 3 mrem total body S 10 mrem to any organ 2.92E--3 MPC's i.:16E-9 uci/cc 127E-1 mrem 6.23E-5 mrem
Yes
'2.92E-3 MPC's 3.57E-5 curies 4.02E-.5 curies' 1.27E-7 mrem 6-.23E-5 mrem 1.27E-7 mrem*
6.23E-5 mrem m
pn
-6.5' ts.5 itanaara.Units
.7.6 Flow'- 14.4 million gallons per day'..
1000gallons
VERMONT STATE RAD HEALTH REGULATIONS(Part 5, Chap.
3)
- 1. Radioactive Material(except tritium and dissolved noble gases S IE-7 uci/mlW Additional action level4
- 1
>2% of iE-7(or 2E-9)uci/ml*
Requires investigation, programs to reduce releases and report to Vt. Board of Health within 14 days.
(see regulation for additional details)
>4% of IE-7(or 4E-9)uci/mlW.
Requires investigation, immediate report to the Vt. Board of Health and then, < 14days later, f0llowup report to Vt. Board of Health(see regulation for additional details) 4.10E-9 uci/ml 4.10E-9 uci/ml 4.10E-9 uci/ml
- 2. Tritium -
K 3E-3 uci/mi 5.72E-9 (see regulation for additional quarterly limits)
- 3. Dissolved noble gases -
K 4E-5 uci/ml 1.16E-9
.(see regulation for additional quarterly limits)
I uci/ml uci/ml Performed by
,2 Reviewed b!9?-
4;
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.,A, W.4-:0 1-T-I Yk.
FR2c),4j...
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SUMMARY
OF APPLICABLE LIMITS AND "JUSTIFIABLE" CALCULATED VALUES FOR LIQUID RELEASE OF 8/14/92 Bases -
The "Calculated Value is based upon the assumption that 1000 gallons of radioactive water was pumped Out of the TB Clean Sump and discharged, through the normal flow.path, to the river..:
The calculation' assumes dilution by. the flow of -Circulating Water(360000 gpm) occurring concurrently with this discharge.
APPLICABLE LIMITS
.LIQUID RELEASE-.
.'Calcula~te~dValue.
.TECHNICAL SPECIFICATIONS
- Liquid Effluents: Concentrations I
)T S.
3 a*A-I
ýL"+/- I Ufr Ls e1LL+/-ntuU by 10CFR20, App.B, Table II, Col. 2 conc.(Noble Gases excluded) 2.92E-3 MPC's 2)T.S.3.8.A.1 - Total Noble Gases.
Conc.*S 2E-4 uci/cc 1.16E-9 uci/cc Liquid Effluents: Dose 1)Total Body Dose -T.S.3.8.B.1 1.5 mrem in any quarter,,
3 mrem total for year 2)Organ Dose - T.S.3.8.B.1 -
5 mrem in any quarter, 10 mrem total for year 1.27"E-7 mrem 6.23E-5 mrem IOCFR50.72 REPORTING REQUIREMENTS 2 times MPC when averaged over one hour NPDES REPORTING REQUIREMENTS...
2.43E-4 MPC's Unplanned Releases 10CFR20 App B, Table II, Col.2 (1
MPC)
Yes
-:2.92E-3 MPC's Total Radionuclides(excluding tritium):
shall be K 5 curies per year 3.57E-5 curies Total Tritium shall be
- 5 curies per.year 4.02E-5 curies Dose Calendar quarter -
< 1.5 mrem total body
-. 1.27E-7 nrem Calendar-
< 5 mrem to any organ 6.23E-5 mrem Calendar year K 3 mrem total body 1':.
1.27E-7 mrem.
1-0 mrem to any organ 6.23E-5 mrem
.pH 6.5 to 8.5 Standard.Units"
..".7.6 Flow -
14.4 million gallons per day 1000gallons
VEtAMONT STATE RAD HEALTH REGULATIONS(Part 5, Chap.
3)
- 1. Radioactive Material(except tritium and dissolved noble gases K 1E-7 uci/mlW Additional action levelfs-
>2%.of 1E-7(or 2E-9)uci/mli*r.
Requires investigation, programs to reduce releases and report to Vt. Board of Health within 14 days (see regulation for additional details) 4.10E-9 uci/ml 4.10E-9 uci/ml 4.10E-9 uci/ml
.-W o X.I-1kor 4z-9)uci/m1T
- Requires investigation, immediate report to the Vt. Board of Health and then, < 14days later, followup report to Vt. Board of Health(see regulation for additional details)
- 2. Tritium -
< 3E-3 uci/ml 5.72E-9 uci/ml (see regulation for additional quarterly limits) *
- 3. Dissolved noble gases -. S 4E-5 uci/ml (see regulation for additional quarterly limits) 1.16E-9 uci/ml Performed by Reviewed bYZ Tl4'
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SUMMARY
OF APPLICABLE LIMITS AND "JUSTIFIABLE" CALCULATED VALUES FOR LIQUID RELEASE OF 8/14/92 Bases -
The "Calculated Value is based upon !the a'uiption" that 1000 gallons of radioactive water, was. pumped out of the TB Clean.
Sump and discharged, through the normal flow *path,
.to the river..:.!
The calculation assumes dilution by the lf ow..of Circulating Water(360000 gpm) occurring concurrently with this discharge-..
APPLICABLE LIMITS
.LIQUID RELEASE *
" :.' " t. : "
- ..,;:.CalculatedValue TECHNICAL SPECIFICATIONS
.:Liquid Effluents: Concentrations 1)T.S.3.8.A.1 -
< 1 MPC as determined by 10CFR20, App.B, Table.II, Col..2
- conc.(Noble Gases excluded)
.2.92E-3 MPC's 2)T.S.3.8.A.1 - Total Noble Gases Conc.
< 2E-4 uci/cc 1..16E-9 uci/cc.
Liquid Effluents: Dose 1)Total Body Dose -T.S.3.8.B.1
.1.5 mrem in any quarter, 3 mrem total for year 2)Organ Dose-T.S.3.8.B.1 5 mrem in any quarter, 10 mrem total for year 1.27E-7 mrem 6.23E-5 mrem 10CFR50.72 REPORTING REQUIREMENTS 2 times MPC when averaged over one hour 2.43E-4 MPC'S NPDES REPORTING REQUIREMENTS Unplanned Releases 10CFR20 App B, Table II, Col.2
.IW' 1
)ADf 9 Yes Total Radionuclides(excluding tritium)-*
shall be S 5 curies per year 3.57E-5 curies
. Total Tritium shall be < 5.curies per year.
4.02E-5 curies Dose'.
Calendar quarter -
.1.5 mrem total body
.i.27E-7 m'orem 5 mrem to any organ 6.23E-5 mrem.
Calendar year K
< 3 mrem total body
. 1.27E-7 mreim.u
< 10 mremto any organ...'. 6.23E-5 mrem pH -
- 6.5 to 8.5 Standard*Units
".7.6 lo-144-ilio.glln per da
- l....O.
.".a.-..
l°.
s Flow* -.14.4 million gallons per..day 1000gallons
VERMONT STATE RAD HEALTH REGULATIONS(Part 5, Chap. 3)
.1. Radioactive Material(except tritium and dissolved noble gases 1 1E-7 uci/ml*
Additional action levels*
- 4.1OE-9 uci/mi
- 1 I
Requires investigation, programs to reduce releases and report to Vt. Board of Health within 14 days.
(see regulation for additional details)
>4%* of IE-7(or 4E-9)uci/mlW Requires investigation, immediate report to the Vt. Board of Health and then, < 14days later, followup report to Vt. Board of Health(see regulation for additional details)
- 4.
- 4. 1OE-9 uci/ml uci/ml
- 2. Tritium -
< 3E-3 uci/ml 5.72E-9 uci/ml (see regulation for additional* quarterly.
limits)
- 3. Dissolved noble gases -
4E-5 uci/ml 1.16E-9 uci/ml
- (see regulation for additional quarterly.
limits)
Performed by..
Reviewed b S-tre owo 4,re 4
o(4IyZ24v2ut
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SUMMARY
OF APPLICABLE LIMITS AND "OUTER BOUNDS" CALCULATED VALUES FOR LIQUID RELEASE OF 8/14/92.
Bases The "Calculated Value is based upon' the as'umption that 12000 gallons of radioactive water was pumped out, of the TB Clean Sump and discharged, through the normal flow path, to the river.
The calculation assumes dilution by the, flow of Circulating Water(360000 gpm) occurring concurrently with this discharge.
APPLICABLE LIMITS.'
LIQUID"RELEASE CalculatedValue TECHNICAL SPECIFICATIONS Liauid Effluents: Concentrations I)T.S.3.8.A.1 -
1 1 MPC as determined by 10CFR20, App.B, Table II, Col. 2..
conc. (Noble Gases excluded) 2)T.S.3.8.A.1 Total Noble Gases.
Conc. S 2E-4 uci/cc Liquid Effluents: Dose 2.92E-3 MPC's
- 1. 16E -9.
ic i/cc 1.52E-6 rnrem, 1)Total Body Dose -T.S.3.8.B.1 1.5 mrem in any quarter, 3 mrem total for year 2)organ Dose - T.S.3.8.B.1 -
5 mrem in any quarter, 10 mrem total for year' IOCFR5O.72 REPORTING REQUIREMENTS 2 times MPC when averaged over one hour NPDES REPORTING REQUIREMENTS 7.47E-4 mrem 2.92E-34MPC's.
Unplanned Releases iOCFR20 App B, Table II, Col.2
(< 1 MPC)
Yes 2.92E-3 MPC' Total Radionuclides(excluding tritium) shall be < 5 curies per year.
4.42E-4 curies Total Tritium shall be K 5 curies per year 4.82E-4 curies
.Dose.
Calendar quarter -
< 1.5 mrem total body 1*52E-6 `rerm
-<5 mrem to-any organ 7.47E-4 mrem Calendar year
< 3 mrem total body.
1.52E-6 mrem 10imrem to any organ, 7.:47E-4 mrem pH 6.5 to 8.5 Standard Units Flow -
14.4 million' gallons per' day 7.6 12000 gallons
VERMONT STATE RAD HEALTH REGULATIONS(Part 5, Chap. 3)
- 1. Radioactive Material(except tritium and dissolved noble gases < 1E-7 uci/m14 Additional action levels
>2% of IE-7(or 2E-9)uci/ml*
Requires investigation, programs to reduce releases and report to Vt. Board of Health Within 14 days (see regulation for additional details).-
- 4. 1OE-9 uci/ml 4.10E-9 uci/ml I.
>4% of 1E-7(or 4E-9)uci/ml4 4.1i Requires investigation, immediate report to the Vt. Board of Health and then, < 14days later, followup report to Vt. Board of Health(see regulation for additional details)
Tritium -
Dissolved noble gases-
< 4E-5 uci/ml.
, 1.1.6E-9 uci/x
.(see regulation for additional quarterly limits) m1 AA; A4
SUMMARY
OF APPLICABLE LIMITS AND "OUTER BOUNDS" CALCULATED VALUES FOR LIQUID RELEASE OF 8/14/92.
Bases -
The "Calculated Value is based upon the asSumnption thaft :
12000 gallons of radioactive water was pumped out 'of the TB Clean"'.:
Sump and discharged, through the normal flow.path," to the river..
The. calculation assumes dilution
- by..the flow. of.'Circulating Water(360000 gpm) occurring concurrently with this discharge.:"".
- APPLICABLE LIMITS LIQUID.RELEASE
"':. ":,-,...Ca culatedVal'ie'.
TECHNICAL SPECIFICATIONS S"Liquid Effluents: Concentrations 1)T.S.3.8.A.l --S 1 MPC as determined
-by 10CFR20, App.B, Table II, Col..2 conc.(Noble Gases excluded) 2'92E-3 MPC s" 2)T.S.3.8.A.1 Total Noble Gases Conc. S 2E-4 uci/cc 1.16E-9 uci/cdc Liquid Effluents: Dose 1)Total Body Dose -T.s.3.8.B.I 1.5 mrem in any quarter, 3.mrem total for year
.1.52E-6 mrem 2)Organ Dose - T.S.3.8.B.1 -
5mrem in any quarter,
.10 mrem total for year 10CFR50.72 REPORTING REQUIREMENTS 2 times MPC when averaged over one hour NPDES REPORTING REQUIREMENTS 7.47E-4 mrem 2.92E-3 MPC's Unplanned Releases
.."Yes' 10CFR20 App B,.Table -II, Col.2 (1
MPC) 2.92E-3 MPCS' Total Radionuclides(excluding tritium) shall be S 5. curies per year
. 4.42E,4 curies per.
~
~
4.4.2 Total Tritium shall be S 5 curies peryear :
4.82E-4 'curies
- Dose Calendar quarter -
1.5.mrem total body.....";52E6"mre
< 5 mre"'to-any organ.
7.47E-4 mrem alendrmre total bodyy*
3
- ..h 1.52E 6 mtrerm.
1 10 mrem to any organ 7 47E 4 mrem.
pH
- 6.5 to 8.5 Standard Unxts 7.6 Flow-14.4. million gallons per day
.12000 gallons' Fi w' 14. mi l o gal 0***.i:*
VERMONT STATE RAD HEALTH REGULATIONS(Part 5, Chap.
3)
- 1. Radioactive Material(except tritium and dissolved noble gases 1
1E-7 uci/m14 Additional action levels 4
>2% of IE-7(or 2E-9)uci/ml.
Requires investigation, programs to reduce releases and report to Vt. Board of Health within 14 days (see regulation for additional details)
>4% of lE-7(or 4E-9)uci/ml4 SRequires investigation, immediate report to the Vt. Board of Health and then, < 14days later,-
followup report to Vt. Board of Health(see regulation for additional
- details)..
- 2. Tritium -
3E-3 uci/ml (see regulation for additional quarterly limits) 4.10E-9guci/ml 4.10E-9 u~ci'/ml 4.10E-9 uci/mi 5.72E-9 uci/ml 1.16E-9 uci/ml i
- 3. Dissolved noble gases -
- 4E-5 uci/mi (see regulation for-.additional quarterly limits)
L 46E.
44A.~.44 "kV 4dd/
nnc~'
F)
~
z p
SUMMARY
OF APPLICABLE LIMITS AND "OUTER BOUNDS" CALCULATED VALUES FOR LIQUID RELEASE OF 8/14/92 Bases The "Calculated Value is based.upon the* assumption that 12000 gallons of radioactive water, was pumped out."f the TB Clean Sump and discharged, through the normal flw
.path, to the river'..
The calculation. assumes dilution by the ;.flow.bf *Circulating Water(360000 gpm) occurring concurrently with this discharge:.:..
APPLICABLE LIMITS LIQUID RELEASE
.... CalculatedValuei-i TECHNICAL SPECIFICATIONS Liquid Effluents: Concentrations 1IT..S.3.8.A.1 -
< 1 MPC as determined
'by 10CFR2O, App.B, Table.II, Col. 2.
conc. (Noble Gases excluded) 2)T.S.3.8.A.1-Total Noble Gases Conc. S 2E-4 uci/cc-Liquid Effluents: Dose 2.92E-3 MPC's 1.16E-9 uci/cc 1)Total Body Dose -T.S.3.8.B.l 1.5 mrem in any quarter, 3 mrem total for year 2)Organ Dose - T.S.3.8.B.1 -
5 mrem in any quarter, 10 mrem total for year 1.52E-6 mrem 7.417E-4 mrem 2.92E-3 MPC's 10CFR50.72 REPORTING REQUIREMENTS 2 times MPC when averaged over one hour NPDES REPORTING REQUIREMENTS Unplanned Releases
- i * *.
Yes.
10CFR20 App B, Table II, Col.2 92E-.
PCs
. ( 1MPC)
E-3 Total Radionuclides(excluding' tritium) shall be e 5 curies per. year.
4.42E-4 curies.
.Total Tritium shall be 55 curies per year ""4.82E-4 ries; Dose..
Calendar quarter -K 1.5 mrem. total, o'dy
Calendar yearter 3 ir-em total0body"-.'52E-6 mrem 1-10 mrem to any organ
'h 7.-47E-4 mrem pH 6.5 to 8.5 Standard Units 7.6
. Flow -
14.4 million gallons per day 12000 gallons*
VERMONT STATE RAD HEALTH REGULATIONS(Part 5, Chap. 3)-
- 1. Radioactive Material(except tritium and dissolved noble, gases S 1E-7 uci/m14 4.10E-9 uci/mi Additional action levels
>2% of lE-7(or 2E-9)uci/ml.
Requires investigation, programs to reduce releases and report to Vt. Board of Health within 14 days
- J (see regulation for additional details)
>4% of 1E-7(or 4E-9)ubi/m14 Requires investigation,.
immediate report to the Vt. Board of Health and then, < 14days later,..
followup report to Vt. Board of Health(see regulation for additional.
details) 4.IOE-9 uci/ml 4.1oE-9 uci/ml
- 2. Tritium -
< 3E-3 uci/ml (see regulation for additional quarterly limits)
- 3. Dissolved noble gases -
< 4E-5 uci/ml (see regulation for additional quarterly
.. limits) 5.72E-9 uci/ml 1.16E-9 uci/ml
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OPERATIONS DEPARTMENT MEMORANDUM TO:
S.Skibniowsky DATE:8/18/92 FROM:
J.T.Herron FILE:
SUBJECT:
Condensate spill On-8/14/92 R.
Gerdus and I
needed to evaluate if the notification requirements of 10CFR50.72 had been met which would require us to contact the NRC via the NRC red phone. In order to make the determination with respect to the applicable release limits we assumed that 12000 gallons of water was pumped out of the clean sump to the circ water discharge block. This is an extremely conservative value in that the we assumed one hour of continuous sump pump operation at the capacity of the pump @ 200 gpm.
After further review, a more realistic value of the amount of water discharged from the sump to the circ water discharge block would be @ 1000 gallons.
This is, in my opinion, still very conservative in that at no time during the spill had the water reached the sump enclosure. Operation personnel, in the area at the time of the
- spill, have stated that the only source of contamination believed to have migrated to the sump was from the floor drains. It is our belief that the floor drain plugs, that are present to prevent the intrusion of contamination into the clean sump, were not water tight. The conservative 1000 gallons figure was based on the following.
1-The TBCCW clean sump pump timer readings have shown an average of @ 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> of operation per week over the past month.
2-Based on #1 above the TBCCW clean sump pumps operate @ 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per day which. in turn correlate to 1 pump down per hour.
3-The sump volume is
@500 gal.
4-Since the event went on for @ 45 min. a conservative approach of 2 pump downs in the 45 min. would be appropriate.
5-The float system in the sump is set up to pump @ half-.of the tank volume or.@ 250 gallons.
In conclusion I would concur with your assumption to use 1000 gallons of radioactive water to calculate the liquid release values for the 8/14/92 liquid release.
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EVRLUATION OF TBCCW SUMP RELEASE PATHWAY - 8/14/92 Calculations Assumptions The TBCCW sump pump is rated at 200 gpm.
The worst case scenario is that this sump ran for one hour while radioactive liquid from the backwash receiving tank was overflowing onto the floor and leaking into the sump.-
The one hour duration was based upon the fact that the SW rad monitýor alarm came in high at 1338 and the TBCCW clean sump was secured at 1430.
Chemistry technicians sampled the clean sump at 1410 and the TBCCW area floor at 1405.
Isotopic analyses of both the floor and the sump are attached.
A tritium analysis was performed on the sump sample and found to be 1.06E-5 uci/ml at 1410..
- . 13Only 4euir radionuclides were identified in the 'clean sump(I-"
1311A 1-133, 1-134 and 1-135) probably due to the shorter count time of this sample.
Therefore, the floor sample data was used to extrapolate the probable concentrations of all identified radionuclides possible in'the sump sample.
This ratio was set at 600 to 1 based upon the worst case radioiodine r4tio.
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TOTAL BODY AND MAXIMUM ORGAN DOSES FROM LIQUID RADWASTE RELEASES SoR
\\LOOO 5\\
-MONTH__
YEAR_
curies Total Body Radionuclide Released X Dose Factor =
H-3 Na-24 Cr-51 Mn-54 Mn-56 Fe-59 Co-58 Co-60
- Zn-64 Sr-89 (1)
Sr-90 (1)
Zr-95 Mo-99 To-99m Sb-124
.1-131 1-132 1-133 1-135 Cs-134 Cs-137 Ba-140 Ce-141 W-187
- q. L C-q X X
x x
X x
X X
X X
X x
~ X X
~ X I A..
V_; Ca X X
2.06E-04' 3*38E-02
- 3. lOE-04 2#
608E-O01'.
8.53E-06 2.49E-01
- 5. 97E-;02 2 *13E-01.
- 8. 06E+00 2 *5SE-01 4.23E+01 4.21E-04.
4.79E-03 S. 04E-06 8.44E-03' 2.57E-02
- j. lOE-06 3.31E-03 3.16E-04 1.28E+02
- 7. 58E+01.
4.08BE-03 2.31E-05 1418E-02
=
=
=
=
=
=
=
=
=
=
=
=
(2A) innem:
- t. r-F-72 Max..organ (213)
(then Ci) X Dose Factor
%Ro.m
.X 2.06E-64
_________R X 3,38E-02 X. 6.96E-02
=
X 3. OOE+OO X,.ý.5.29H-03 X 1484E+00 X 4.34E-61 X 1. 28E+00
- X 1. 64E+01 X 8.91E+00 X 1. 67E+02 X 1636Eý-01 X 4.51E-02'.
______=_
X 2.33E-04 F'~'
¶
\\-5E-1cJ X 2.22E-01
- X 1.47E+01
.~,F-L4 X 1. 29E-04
~
-35~
.C
- X 1. 60E+02 X 1421E+02 X 9M7E-02 V___
___6 X 4.10E-02 X 8.90E+00 D
(SUM)
-q wr MO.
mRem(3B)
D lq
- , (SUH) tb mRem (3A)
(1)
Use most recent data available for Sr-89 and Sr-90.
(2A) T.S. 3.8.B.1 Limits:. 1.5.mRem in any quarter, 3.0 mRem per year.
(See also 3.8*C.1 and 3.8.M.l.)
VYOPF 4609.01 OP 4609 Rev. 8 Page I of 1 RT No. llFO16163 (2B) T.S. 368.B.1.Limits:
5 mRem in any quarter, 10 mRem per year.
(3B)
1L (,
0-3%~
X 33
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uCi/g W
e Demin Resin Data Co6O 73 1E-05 7.300E-04 14 IE-06 4.500E-05 FeSS 503
-06 5.030E-04 N159
-36 lE-
-3.600E-06 Ni63 376 IE-06
.7760E-04 Pu238 1
IE-07
- 1.
OOEE-07 Pu239 19 1E-07 1.900 06 Pu241 55 1E-06 5.500E-O Am241 46 1E-07 4.600E-06 Cm242 4
1E-07 4.OOOE-07 Cm244
-68 1E-09 -6.800E-08 Np237
-24 1E-06 -2.400E-05 Calculated MDA 5.60E-04 2.90E-05 5.10E-05 2.20E-05 1.20E-04 4.SOE-06 3.60E-06 1.90E-04
""..30E-06 Value Used 7.300E-04 4.500E-05 5.030E-04 2.200E-05 3.760E-04 4.500E-06 3.600E-06 1.900E-04 5.300E-06 3.8OOE-06 2.600E-06 Co60 Scaling Factor I.OOOE+00 6.164E-02 6.890E-01 3.014E-02 5.151E-01 6.164E-03 4.932E-03 2.603E-01 7.260E-03 5.205E-03 3.562E-03 7.808E-02 Pu239 Scaling Factor 1.25E+00 1.OOE+0O 5.28E+/-01.
1.47E+00 1.06E+00 7.22E-01 1.58E+01 3.8" 2.601 Cs137 Sr9o Tc99 1129 595 134
-36 8
1E-65 1E-07 1E-07 IE-07 5.'950E-03 1.340E-'05
-3.600E-06 8.000E-07 5.00E-04 1.40E-05 8.00E-06 1.20E-05 Cs Scal in Sactor 1.00 +00 2.353E-1.345E-03 2.017E-03 5.950E-03 1.400E-05 8.OOOE-06 1.200E-05 Condemin Resin Data(Avg of A Co60 751 IE-03 7.510E-01 C 14 111.5 IE-05 1.115E-03 Fe5S 408.5 1E-03 4.085E-01 Ni59
-1 IE-05 -1.000E-05 Ni63 1552 1E-04 1.552E-01 Pu238 15 1E-06 1.500E-05 Pu239 32.5 1E-07 3.250E-06 Pu241383.5 1E-04 3.835E-02 Am241 9
1E-06 9.OOOE-06 Cm242 54 1E-07 5.400E-06 Cm244 17.8 1E-07 1.780E-06 Np237-183.
1E-06 -1.835E-04
& e) 6.ISE-01 3.95E-04 4.25E-03 1.55E-03 8.85E-03 3.S5E-05 2.55E-05 2.OOE-02 5.45E-05 2.80E-05 2.35E-05 5.05E-04 7.510E-01 1.115E-03 4.085E-01 1.550E-03 1.552E-01 3.550E-05 2.550E-05 3.835E-02 5.450E-05 2.800E-05 2.350E-05 5.050E-04 1.OOOE+00 1.485E-03 5.439E-01 2.064E-03 2.067E-01 4.727E-05 3.395E-05 5.107E-02 7.257E-05 3.728E-05 3.129E-05 6.724E-04 Cs Scaling Factor I.OooE+O0 7.922E-02 1.196E-02 1.134E-03 Ok.500\\V t I
1.39E+00 1.OOE+O0 1.50E+03 2.14E+00 1.10E+00 9.22E-01 1.48E+01 J
Cs137 397 Sr9o 314.5 Tc99
-4 1129 2
1E-03 IE-04 IE-04 1E-05 3.970E-01 3.145E-02
-4.OOOE-04 2.OOOE-05 6.SOE..02 2.55E-03 4.75E-03 4.50E-04 5.0 t-,3 3.970E-01 3.145E-02 4.750E-03 4.500E-04 G- '69 3-7 -7.5 1 r,- - -3 S.-7-75 E ýj
- °.
MAILED AP:3019e YANKEE ATOIXC ILECTRIC COIPANY ENVIRONrNLTAL LABORATORY 10 CFX Part 50/61 Analysis RePOrt Page 1 of 2 Laboratory tSepte Numler:
203032#
Sempts Sul:mfssion Codes VRES0580992 Media Typez Resin Total Amt of "tol Senti 0.11 a Sa"to Description; Customer:
Vermiont Yankee si$ple Reference Data:
February 26, 1992 Date Splpe Received:
March 5. 1992 Report Date: April 29, 1992 NHO Condensate Rosin Atiquot Weight Processed Analysis
[a]
Date Activity Concentration I 10 Overall on Reference Date
. Elci/vl Detectable Concentration (A) on Refertnce Date CALCULATED REQUIRED WIt/0)
EALW]
Notecs)
'Analysis Requested H-3 C-14 Fe-55 111-59 111-63 Sr-89 Sr*90 Ic-99 up-237 Pu-238 Pu-239,240 Pu-241 Am-241 Ciu-242 Czu-243,244 1-129 9.600E*04
¶.2?00E-02 2.1000f-03 a.4DOOE-04 I.OOOOE-03 2.1000E-03
- 2. 1000e-03 9.200of-04 2.12002-03 2.11 OOE-03 2.11002-03 4.90OOE-D4 2.1100E-03 2.11002-031 2.1100E-03 6.50002-03 04/03/92
- 03128/92 03/18/92 03/27/92 03/23/92 04/02/92 04/02/9Z 04/23/PZ 03/18/92 03/17/92 03/17/92 0,4/07/92 03/16/92
-03116/92 03/16/92 04/13/92 C
C C
C C
C C
(
C C
C C
C C
C C
29 2 29 )E-04 149 i 19 )E-05 421
- 35 )E403
-23 e 41 )E05 222
- 19 )E-03 565 4
43 )E-03 202 a 19')E-04
-9 A 17 )E-04
-176 t 82 )E-06 13
- 21 )E-06
-39 a 22 )E-D7 726 1 70.)E-04 10 t*16 )E-06 124 1 95 )E*07 48
- 62 )E-07 9 t 13 )9-05 49 E-04 45 E-05 40 e-04 15 E-04 88 E-04 52 E-04 21 E-04 57 E-04
&.* E-05 51 E-06 33 E-06 11 E-03 56 E-06 21 E-06 21 E-06 53 E-05 4,0E-01 8.0E-02 7.OE+O0 2.2E+00 3.5e-02 4.OE-D4 3.OE-02 I.0E-03 I.0E-03 1.0E-03 3.5E-02 1.0E-03 2.OE-01 1.0E-03 B.OE-04 e
B C
S
.3 B
Note*s):
1-A -Calculated NDCs are a-postoriorl values.
2 - Results are statistically positive at the 99.9% confidence level (activity it greeter then three tlmes the standard deviation).
C - Requireid MOC is for activated metal.
Rev*ewed by e
E. K.l4)reno aeC.ury Jsfýei C. kurray Updated to include all requested 10 CFR analyses.
e.'IP a,
MAILED APR 301 YANUE ATOMIC ELECTRIC COMPANY ENVIRONMENTAL LABORATORY 10 CFR Part 50161 Analysis keort m..........................
Laboratory emple Nurber:.Z03032
&a"le Submission Code:
VRE905*
092 Medl Type:
Resin Total Amt of smvlte Sent:
0.11 g Sample
Description:
Pace 2 of 2 Customer:
Vermont Yankee Sample Reference Date:
february 26, 1992 Date $ample Received:
Marc 5, 199M Cotrit Date:
March 9, 1992 Report Datat AprIl 29, 1992 "30 Corgle*ata ResIn Al iquot Iguight.
Processed (91 Isotope Activity Concentration i 1r Overall on Reference Date
[AC$lt l
. Miniffum Detectable Concentration (A) on Reference Date CALCULATED REQUIRED
[ECI/9)
[ACI/03 Note(s)
Antalysi Requested Gaam Scan 0.0424 Cr--1 Nn-54 Co-57 Co-38 Fe-59 Co-60 Zn-65 Nb-94 Zr-95 Rb-95 Ru-i03 Ru-106 Ag-1OBM AV-110m Sb-124 Sb-125 CO-134 Cs -137 on-140 La-140 Ce-i141 Ce-144 C
(.
C
(
C
(
(
(
C
(
C
(
(
(
(
(
(
12 a 21 125 a 19 13 23
-27 +/- 25
-50 a54 946 a 54 1p86 82
.44 25
-6 38 12 a 25 18 a 22
- 6 +/- 19 5 a 19 34 33 29 23 4 t 58 3S0 k 24 995 a 59 8 i 14 334 a 38 62 a 55
-50 a 19
)E-02
)E-03
)E-03
)E-03
)E-03
)E-03
)E-03
)E-03
)E-03
)E-03
)E-03
)E-03
)E-03
)E-03
)E-03
)E-03
)E-03
)E-03
)E-02 85 E-02 61 E-03, 89 E.03 10 E-02 23 E-0Z 67 E-03 17
'-02 11 E-02 16 E-02 10 E-02 90 E-03 79 E-02 77 E-03 14 E-02 B4 E-03 24 E-02 75 E-03 75 E-03 56 E-02 13 E-02 21 E-02 72 E-02 7.OE*00 7.0E÷DO 7I.DE+00
?.OE*00 7.OE+00.
2.0E-03 7.OE+00 7.02+00
- 7. 0E÷00 7.0E+00 7.OE.0O 7.0E.00 7.0E+00 7f.0E+00 7.W+00 I.OE-02 L
74OE+O0 7OE÷00 B
B C
B B
Not*Cs):
A - Calculated MDCs are &-posterlorl values.
- Results are statistialley positive at the 99.9% confidence level Cactivlty Is greater than three times the standard deviation).
C - Re*tred HOC is for activated mmtal.
S E. M.1 reno Reviewed by a
Jamee C. kurray
. MAILED YANIKEE ATCHIC ELECTRIC COMIPANY ENVIROUMENTAL LANORATORY 10 CFR Part 50/61 Anatysis Report g..........
Paeg I of 2 Laboratory Sample Number:
Z03031 Sample Sukalmslon Codet VRES05AO992 media Type:
Resin Total Amt tf Iapte Sent:
0.174 g Sanple Descriptlon:
Customer:
Vermont Yankee supl. Reference Oato' February 26, 1992 Date Sarmple Received:
March 5, 1992 Report Watei April 29, 1992 CONDENSATE RESIN "Au Aliquat Weight Processed Anlysis tg)
Date Activity Concentration i iv Overatt on Reference Date
(*ci/Is Niniui Detectable Concentration (A) on Reference Date CALCULATED REQUIRED rtcvisg (5CI//fI NoteCs)
Analysis Requcsted H-3 C-14 Fe-55 H1-59 NI-63 Sr-B9 Sr-90 Tc-99 Np-2 37 Pu-238 Pu-239,z40 Pu-241 Am-24,1 Cm-242 Cm-243,244 1-129 1.4200E-03 1.6600(-02 1.9600E-03 7.7OOOE-04 1.000OE,03 1.9600D-03 i.9600E-03 1.37OOE-03 1.9eaGE-03 1.96002-03" 1.9600E-03 6.50001-04 1.9600E-03 1.9600E-03 1.9600E-03 1.08008-02 04/10/92 03/28/92 03/18/92 03/25/92 03/23/92 04/02/92 04/02192 04/23/92 03/18/92 03/17/92 03f17/92 04/07/92 03/16/92 03/16/92 03/16/92 04/10/92 C
C C
C C
C C
C C
C C
C C
C C
31 1 10 )E-04 74 t 13 )E-05 396 1 33 )E-03 21 k 47 )E-05 884 1 82 )E-04 190 t 13 KE-03 427 1 32 )E-04 I 1 12 A8-04
-191 1 90 )E*06 Ir +/-.10 )E-06 115 1 80 )E-07 411 29 )E-04 B 1 17 )E-06
-16 1 90 )E-07
-125 - 89 )E-08 101 +/-171 )E-06 17 E-04 34 E-05 45 E-04 16 E*04 89 E-04 56 E-04 30 E-04 38 E-04 53 E-05 20 E-06 18 E-06 91 E-04 53 E-06 35 E-06 26 E-06 29 E-05 4.0E-01 8.08-02 7.0t0DO 2.ZE+00 3.5E-02 4.0f-04 3.CE-02 1.0E-03 1.0E-03 10E-03 3.5E-02 1.0E-03 2.0E-01 1.OE-03
.8.0-04 B
9 U
C B
S Note(s):
A - Calculated M4Cs are a-posteriori values.'
8 - Results are statisticalty positive at the 99.9t confidence level (activity to greater then three times the standard deviation).
C - Rauired MFC Is for activated metal.
Reviewed by M
oreio Updated to include all requested 20 CFR 61 analyses.
MAILED APR 3, 0 YANKEE ATOMIC ELECTRIC COMPANY ENVIRONXENTAL LABORATORY 10 CFR Part 50161 Analysis Report Page 2 of 2 Laboratory sempte NWmr:
Z03031 Sanzea Submtiseion Code:
VRE$OSA0992 Media Types Resin Total Amt of $aurpto Sent:
0.174 0 Custower:
Smpte Reference Date:
Date SImpte Received:
Count Date:
Report Dates Vermort Yankee February 26, 1992 March 5, 1992 March 9, 1992 Aprit 29, 1992 Simple Description; CONDENSATE RESIN "A,"
o......b Activity Concentration A lc OveralL an Reference Date
- CLi/g1 Al iquot welght Processed Detectable Concentration (A) on Reference Date CALCULATED REDUIRED ElxCI/9 ci/9Cll Note(s)
Analysis Requested Isotope Camme scan 0.0387 Cr-51 Mn-54 Co-57 Co-58 Fe-59 CO-60 Zn-65 Nb-94 Zr-95 Nhb-95
.Ru-103 RU-106 Ag-liom 5b-124 sb-'125 Ca-134 Cg-137 sa-140 Le-140 Ce-141 CS-144 C
(
C C
C C
C C
C C
C C
C
(
C C
C C
C C
C 8 3 17 )E-02 86 a 15 )E-03
-4 15 )E-03
-29 a 20 )E-03 B
42 )E-03 556 a 33 )E-03
- 432, 48 )E-03
-1 18 )E-03 15
- 29 )E-03
-11 a 21 )E-03 16 17 )E-03
- 0 a 15 )!-02
-12 a 15 )E-03
-60 a 27 )E-03 43 a 21 )E-03
-35 45 KE-03 166 a 14 )E-03 4"
30 )E-03 23 a 10 )E-02 220 a 30 )E-03 71 a 35 )E-03
-23 1 12 )E-02 67 E-02 52 S-03.1 59 E-03 84 E-03 18 e-oz 56 E-03 15 E-02 74 E-03 12 E-02 90 E-03 67 E-03 60 E'0Z 60 E-03 12 E.02 84 E-03 18 Eý-02 58 E-03 55 E-03 39 E-0Z 14 E-0Z 14f E-02 47 E-02 7.OE+O0 7.0E+O0 7.OE+00 7.OE+00 7.OE+00 2.OE-03 7.OE+O0 7.OE!O0.
7.0E100 7.0i*00O 7.6f+00 7.09+00 7.0f+DO 7.OE+00 7.OE00 i.OE-OZ 9
B B
C B
II B
7.0E400 7.VE+00
- ý........
°......
o...............o........T..........*
°..........
Note~s):
A - Calculated MD C are a-poaterlorl values.
5 - Results are statisticalty positive at the 99.9% confidence level (activity Is greater than~three time the standard deviation).
C - Required HOC to for activated owtal.
Reviewed by Eorenfo
,91James C. Mu~rra 7
MEMORANDUM To: Distribution September 8, 1992 From: D. Voland Vernon
Subject:
Offsite Dose Calculations -
August 1992 Attached is a copy of the offsite doses calculated for the month of August 1992.
If you have any questions concerning this information, please contact me at your earliest convenience.
copy with attachments:
J.T. Herron R.D. Pagodin J.T. McCarthy S.P. Skibniowsky M.S. Strum (YNSD-Bolton)
G.D. Weyman Chemistry Correspondence Files Chemistry Completed Forms Files
IN TOTAL BODY AND MAXIMUM ORGAN DOSES FROM LIQUID RADWASTE RELEASES MONTH AUG.
YEAR 1992 Radionuclide H-3 Na-24 Cr-51i Mn-54.
Mn-56 Fe-59 Co-58 Co-60
.Zn-64
- Sr-89 (1)
Sr-90 (1)
Zr-95 Mo-99 Tc-99m Sb-124 1-131 1-132 1-133 1-135 Cs-134 Cs-137 Ba-140
- Ce-141 W-187 Curies Total Body Released X Dose Factor =
(2A) mRem:
(then Ci)
Max. Organ X Dose Factor (2B) mRem 4.02E-5 X X
X x
x Xx x
<2.14E-7 X
<I. 78E-8 X X
X I.26E-7 X X
3.46E-6 X
<1.58E-6 X 6.63E-6 X 7.27E-6 X X
X
- 1. 17E-6 X 2.39E-7 X X
2.06E-04 3.38E-02.
- 3. 1OE-04 2.08E-O1 8.53E-06 2.49E-01 5.97E-02 2.13E-O1 8.06E+00 2.55E-01 4.23E+01 4.21E-04 4.79E-03 5.04E-06 8.44E-03 2.57E-02 3.1OE-06 3.31E-03 3.16E-04
- 1. 28E+02 7.58E+01 4.08E-03 2.31E-05 1.18E-02 8.28E-9
<5.46E-8
=
<7.53E = 6.35E-13 8.89E-8 4.90E-12 2.19E-8
=
2.30E-9 4.77E-9
=
5.52E-12
.<9,35E-7 mRem(3A)
X 2.06E-04 X 3.38E-02 X 6.96E-02 X.3.OOE+00 X 5.29E-03 X 1.84E+00 X 4.34E-01 X 1.28E+00 X 1.64E+01 X 8.91E+00 X 1.67E+02 X 1.36E-01 X 4.51E-02 X 2.33E-04 X 2.22E-01 X 1.47E+01 X 1.29E-04 X 1.63E+00 X 5.90E-02 X 1.60E+02 X 1.21E+02 X 9.72E-02 X 4.10E-02 X 8.90E+00 Dr =. (SUM)
=
mo
=
8.28E-9
<1.91E-6
<2.97E-6 2.94E-11 5.09E-5 2.04E-10 1.08E-5 4.29E-7 1.14E-7 9.80E-9
<6.72E-5 mRem(3B)
D
=
(sUM) tb (1) Use most recent data available for Sr-89 and Sr-90.
(2A)
T.S. 3.8.B.1 Limits:
1.5 mRem in any quarter*
3.0 mRem per year.
(See also 3.8.C.1 and 3.8.M.I.)
(3A)
VYOPF 4609.01 OP 4609 Rev. 8 Page I of I RT. No. li.F01.163 (2B) T.S. 3.8.B.1 Limits:
5 mRem in any quarter, 10 mRem.per year.
(3B)
BETA AND GAMMA AIR DOSES FROM NOBLE GASES - TURBINE BUILDING VENTILATION*
YEAR 1992 9
Curies
. Beta (1A) mRad:
Radionuclide Ar-41 Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 Released X Dose Factor =
Gamma (then Ci) X Dose Factor 11 X 9.30E-3 X 3.28E-3 X 2.88E-4 2.45E-2 X 1.97E-3 X 1.95E-3 1.81E-1 X 1.03E-2 9.23E-2 X 2.93E-3 X 1.l1E-3 X 1.48E-3 1.02E-2 X 1.05E-3 1.01E0 X 7.39E-4 1.47E-1 X 2.46E-3 X L.
27E-2 4.37E0. X 4.75E-3 D
=0.55 X airg
=
4.83E-5
=
1.87E-3
= -2.70E-4
=
1.08E-5
=
7.43E-4
=
3.62E-4 2,07E-2 x
x x
x x
x x
x x
x x
1.93t-5
- 1. 23E-3 1.72E-5 6.17E-3
- 1. 52E-2
- 1. 51E-3 (1B)
=
TRad
= 3.O01E-5
= 1. 12R-3
= 1. 40E-3
= 3.62E-6
= 3.38E-3
= 2.83E-4
= 4. 02E-2 X 9.21E-3 (SUM) 2.40E-2 Dairg 0.13 X (SUM) 4.64E-2
=
D 1.32E-2 airg mRad(2A) 10 mRad any quarter, 20 mRad (IA) T.S.3.8.F.I Limit =
per year.
(2A)
7 D
=
6.04E-3 airg mRad(2B)
(IB) T.S.3.8.F.1 Limit = 5 mRad any quarter, 10 maRad per year.
(2B)
Reviewed By VYOPF 4609.05 OP 4609 Rev. 8 Page I of 1 RT No.
11.F01.161
MEMORANDUM VERMONT YANKEE -
VERNON To File Date October 14, 1992 From Deborah Voland Subject REVISION OF AUGUST 1992 DOSE CALCULATIONS Enclosed are 2 pages from the monthly dose calculations from August that have been revised.
The revision of the "Beta and Gamma Air Doses from Noble Gases - Turbine Building Ventilation" was due to a minor error caused by unfamiliarity in using the spreadsheet designed to perform the calculation when the doses were calculated by someone filling in for me when I was on vacation.
The other revision is the result of calculating values for Sr-89 and Sr-90 for the liquid release that occurred in August.
The values were derived from the LLD levels of the. Turbine Sump sample and the scaling factors typical in the associated waste stream.
pee. I-EV4LUATION OF TBCCW SUMP RELEASE PATHWAY -
8/14/92 Calculations Assumptions The TBCCW sump pump is rated at 200.;gpm.
The "worst'- case'.
scenario is that this sump ran for One hour while radioactive' liquid from the backwash receiving tank was overflowing-onto the floor and leaking into the sump.
U-.:
The one hour duration Was based upon the fact tat the"
'Sw rad monitor alarm came in high at 1338 and the. TBCCW clean sump was secured at 1430.-
" hemistry technicians sampled the clean sump at 1410 and the.
-TBCCW area floor at 1405.
Isotopic analyses of both the floor and the sump are attached.
Lo.nly fOeiky radionuclides, were identified in the clean sump(I-
.131, 1-133, 1-134 and 1-135) probabl due to the shorter count time of this sample.
Therefore, the floor sample *data was used. to extrapolate the probable concentrations of all.. identified radionuclides possible in the sump sample.
This ratiowas set at.
600 to 1 based upon the worst case radioiodine.ratio.
(
l1A £.F-_.7_
T_-_~PL F-...
Ica' -I-.
O - *"."
5-.
L-it,-
5/i o
.s Q
O.
1 35l~t
.So._- / Oo
.. s_._/
5,.
.f.._
(, o _ : -. 5".*.% "=-L.
C..
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- X..-_1,,5___.......
a0o X* -.1 *i
,*-*_5._Z'L,=-__*
- ~
- O F.
5 Q.iv~j ~
Wc,,At~r...
~SCAI.D~I-~JLJ
~.
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~
-~-~---V
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-. ~
j.
~3rO oo 0 c~A~.4~o r~o-AL~J c~.Q
,'46c M -
,AI; 4 - A~.%. ~
~
-b.Cr 5..F-xOA
- 2. r--
.A. (St we
_____...%3~77.
z VOL'.
A.3~O..__.
~E~5
-l.
~coSEC_
PA IP
~2t S~1.i5 AO___ _ ~..____
CVI5CSr)'e F.
7-7/f'
~
/-~.
I
~
=A.3 1 A.&
k__
2li3.Y COEz____
J.
LE5
___-.-~-3.3 3-~-~
-~---~-4~ 5.t-E~dO~
~ILAO__.
p
~
-C,,
O ~ ~x~3 7 ~5 c.c,...X.S~ 0 w~w~..C~..~.
C~ ~
1O~~MC~Z
.~!
TOTAL BODY AND MAXIMUH ORGAN DOSES FROM LTQE cureos
'Total Body Radionuallde Released x Dose Factor -
(2A)
- *ef*
(then
' H-3 Nra-24*
Cr-51 Mn-54 Mn-56 Fe-59..
Co-58 co-.60" Zn-64 Sr-89 (1 Sr-90 (1 Zr-95 N0-99 To-99m Sb-124 1-131 1-132 1-133 X"135 C--134 Co-137 Ba-140 Ce-141 W-187:
L
_______X.
___X x
X X
x
~ X A4 jEF5.L.5. X n*
V;_
X IN X
- 2. 06E-04 3.38E-02 3.10E-04 2
- OE-01 80.53E-06 2.*49E-ý01 5,97E-02.
2.13H-01.
8,06H+PO 2.55E-01.
4,23E+01 4.21E-64 4.79E-03
- 5..049-ý06 8.44E-03*
2 *57E-02 3, IOE-06 3.31E-03 3.16E-04 1,28E+02 7.58E+01
- 4. 0GE-;03 2.31E-05
- 1. 1OE-02 2_
2,-
!6t nmE z=
lID RADWASTE RELEJ
.*Max..Organ Ci) X Dose Factor X 2.06E-04 X 3.38E-02 X:6 *.96E-02
- X 3.OOE+00 X..5.29E-03 X 1684E+00 X 4.34E-O1 X 1.28E+00 X 1.64E+01 X 8.91E+00 X 1.67E+02 X 1.36E-01 X 4.51E-02 X 2.33E-04 X 2,22E-01 X 1.47E+01 X 1.29E-04 X 1.63E+00 X 5.90E-02 X 1.60E+02 X 1.21E+02' X 9i72E-02 X 4.10E-02 X 8.90E+00 D liq (SUH) mo MONTH YEAR ____
- (213)
=9
=E m
t paL 10 13 q.
(SUM) tb.'
in.
mnhem (3 A) mnRem (3B)
(1)
Use most recent data available for Sr-89 and Sr-90..
(2A) T,S. 3.8.B1. Limits:.. 1.5, mRem*in any quarter,
.... 3.0 mRem.per..year.
(See also.3.8,C.1 and 3.8.M.1.)
.. (3A)
ODC,..EQ.3- -1.
VYOPF 469
.01 OP 4609 Rev. 8":'.*.'.
- Page,1. of 1 RT No. 11.F01.163.
t (213)
T.S. 3.8.B.1.Limits:
5 mRem in any quarter, 10 aReme per year.
- (3B). ODCH EQ 3-3" Reviewed By
14-AUG-92 15:01:15 VERMONT YANKEE NUCLEAR POWER CORPORATION SAMPLE DA1E.........
14-AUG-92 14:10:00 SAMPLE IDENTIFICATION:
TB CLEAN SUMP TYPE OF SAMPLE.......
LIQUID MARINELLI C-0 SAMPLE QUANTITY......
1000.000 UNITS:
ML SAMPLE GEOMETRY...... :
VY2005 OPERATOR............
SCM EFFICIENCY FILE NAME.:
EFF.VY2005,,
ACQUIRE DATE: 14-AUG-92 14:24:21.
- .FWHM(1332) 1.867 PRESET TIME(ýIVE):.
2000..SEC
- SENSITIVITY:
5.000 ELAPSED REAL'TIME:
2001. SEC
- SHAPE-PARAMETER
- 10.0 %
ELAPSED LIVE:,TIME:
2000. SEC
- NBR ITERATIONS:
10.
DETECTOR..:.
20% HPGE LIBRARY NUCL.LIBl CALIB DATE:
.14-AUG-ý92'00:56:29
- .ENERGY TOLERANCE 1.500KV
- KEV/CHNL..:
0.5001629
- HALF LIFE RATIO 8.00 OFFSET..... :*-0.1059622 KEV
- ABUNDANCE LIMIT 80.00%
Q.:COEFF..:
O.O00E-O1 KEV/C**2
- DECAY TIME (MIN).
14.0:
or-Svc,\\ki x.5i ENERGY WINDOW
.24.*90 TO 2048.56
.1.00-SIGMA %ERR
- PK IT
.1. 0
- 2 0
" 0 4.0
.50 6
2 7.2 8
0 9
0 10 0.
11 0
12 0..
i1 *0 14-.0 15 0
16.0 17 0
18 0-19 0
20 0-21 0
22 0
23 0
ENERGY 249.91 284.07 364.45 417.86 511.04 526.51 529.91 546. 81 637.41 667.81 772.69 836.86 847.23 875.46 884.18 953.99 1038.59 1131.46 1260. 30 1298.49 1457.57 1677.60 1790.53 AREA
.264.
71.
826.
86.
3455.
158.
1239.
84.
37.
240.
.146.
53.
61.
58.
62.
30.
76.
132..
195.
- 13.:
80.
50.
42.
BKGND FWHM CHANNEL LEFT PW" CTS/SEC %ERR 425.
2-48.
167..
125.
168.
,54.
45.
43.
38.
37.
16.
AZ.
52.
18.
19.
18.
26-9.
4.
'9.
0.
- 1.21.
- 1. 45
- 1. 26 2.53 1.53 1.33 1.49 1.27 1.53 1.75'
-2.11
- 1. I1 1.32 1.01 1.74 1.87 1.70 1.51 1.42
- 2.44
.499.87 568.17 728.88 835.67 1021.96 1052.88
.1059.68 1093.49 1274.62 1335.40 1545.09 1673.38 1694.12 1750.57 1768.00 1907.56 2076.71 2262.40 2519.99 2596.36 2914.40 3354'. 32 3580.10 494 12 1.32E-01 565 8 3.56E-02.
724 9 4.13E-01 829 12 4.28E-02 1014 22 1.73E 00 1049 17 7.88E-02 1049 17 6.19E-01 1089 12 4.20E-02 1268 10 1.86E-02 1329 15.1.20E.1538 13*.7.28E-02 1668 11A2.65E-02 1687 14 3.03E-02 1743.
15 2.90E-02 1763 11 3.08E-02 19"02 11 1.50E-02 2069-17 3.80E-02 2258 10 6.58E-02 2511:
18 9.73E-02 2592 10 6.52E-03 2905 22 4.OOE-02.
3348 15 2.50E-02 3573 13 2.11E-02 17.3 40.7 4.6
- .30.0 2.0 10.8.1 3.0 20.2.
38.0 9.0 11.5 24.3
'27.2 20.8 20.8
.40.4 20.6
.10.1 8.0 52.6 13.1 14.1
.19.4 FIT
.. 36E 00
- 0. 1.86
- 4.
'1.75 PEAK SEARCH COMPLETED (REV 15.7)
SUMMARY
OF NUCLIDE ACTIVITY TOTAL PEAKS IN SPECTRUM UNIDENTIFIED PEAKS IDENTIFIED IN
SUMMARY
REPORT PAGE 1
23 19 14 60.87%
FISSION GAS NUCLIDE SBHR XE-135 FG XE-135M FG FISSION PRODUCT
.HLIFE.
- 9. OH
- 15. 65M DECAY 1.040 3.614 UCI /UNIT
- 2. 131E*-7 8.495E -7
.1,00-SIGMA ERROR 3.690E -8.
9.141E -8 1.00-SIGMA
%ERR
.17.32
.10.76 NUCLIDE 1-131 1-132 1-133 1-134 1-135 SBHR FP
- FP
.FP FP
.FP
- HLIFE 8.04D
- 2. 30H
- 20. 80H
- 52. 60M 6.61H DECAY UCI /UNIT 1.002 9.131E -7
.1.167 4.189E -7.
1.017 1.753E -6 1.493.
2.799E -7 1.056 1.920E -6
- 1.
00-SIGMA.
ERROR
- 4.185E -8 3.750E -8 5.285E -8.
5.830E -8 1.527E -7 1.00-SIGMA
%ERR 4.58 8.95.
3.02
' 20.83 "796
14-AUG-92 14:20: 22 VERMONT YANKEE NUCLEAR POWER CORPORATION SAMPLE DAYE..........
14-AUG-92 14:05:00 SAMPLE IDENTIFICATION:.
TB 222 SPILL TYPE OF SAMPLE.......
23ML'SCINT.
VIAL SAMPLE QUANTITY......
23.00000.
UNITS:
ML SAMPLE GEOMETRY......
VY2004 OPERATOR."
GR
-EFFICIENCY FILE NAME.:
EFF.VY20047,
&4j~
'e~-
ACQUIRE DATE:
14-AUG-92 PRESET TIME(IIVE):
ELAPSED REAL'TIME:
ELAPSED LIVE*-TIME:
14:11:45 500. SEC 508. SEC 500. SEC
- FWHM(-1332)
- SENSITIVITY:
- SHAPE PARAMETER
- NBR ITERATIONS:
- 1.867 5.000 10.0 %
10.
DETECTOR..:
20% HPGE
- LIBRARY NUCL.LIB1.
CALIB*DATE:
14-AUG-92 00:56:04.'
- ENERGY TOLERANCE 1.500KV KEV/CHNL..:
- 0*5001629
- HALF LIFE RATIO*
8.00 OFFSET....: -0. 1059622 KEV
- ABUNDANCE LIMIT 80.00%.
Q." COEFF..:
O.OOOE-01 KEV/C**2
- -DECAY TIME (MIN).
6.0 ENERGY WINDOW'.
24.90T0 1.00-SIGMA %ERR 2048.56 1
23 4
5.
6 7
10 11 12 13 14 15 16 17 18 20 21 23 IT ENERGY O*
80.30 0
140.56 0
145.55
- 6.
162.74 6
165.88 0
220.46 0
249.77 5.284*. 27 5
288.46 0
328.80 0
364.49 0.417.86 0
423.50 0
434.28.
0 487.07.
0 511.00 2
522.60 2
526.62 2.529.92 0.. 537.21 0
546.52 0
555.57.
0 595.47 AREA BKGND
.FWHM 1079.
643.
671.
.372.
1891.
432.
4786.
752.
596.
433.
.8637.
563.
- 156.
204.
933.
28700.
399.*
2118.
13207.
537.
821.
.1134.
.194.
3153.
1.52 160.75 2543.
0.94 281.24.
1928.
-1.13 291.21 1985.
1.13 325.59 1654.
1.04 331.86 2262.
.1.15 440.98 2705.
1.12 499.59 1685.
1.13 568.58 1775.
1.12 576.94
.2218.
1.00 657.60 2304.
.1.19
.728.94 1040.
1.21 835.66 855..
1.01 846.94 1498.
4..49 868.48.
998.
1.27-
'974.03.
2006.
2.62 1021.88
.414..
1.29 -1045.07.
599.
1.43 1053.11 448.
1.31 1059.70 636.
1425. 1074.28 464..1.33 1092.90
.546.
1.30 1110.99 416.
.1.39 1190.76 155 277.
- 288
.322 322 437
.494 562 562
- 654 722 832 842 862 968 1014 1042 1042
.1042 1069 1088 1105 1186 CHANNEL*LEFT PW CTS/SEC. %ERR 12 2.16E 00 9 1.29E00 7 1.34E 00 15 7.44E-01 15 3*78E 00 8 8. 64E-01 11 9.57E 00 20.1.50E 00 20 1.19E 00
.8 8.66E-01 14 1.73E 01 11/:1.13E 00 9 3.11E-01
.16 4.08E-01 13 1.87E 00 19'5.74E 01 24 7.98E-01 24:4'.24E 00" 242.64E 01 11 1.07E'00 10 1.64E 00 12'2.27E'00 10 3.87E-01 10.9 14.7.
11.6.
20.5 4.1 19.5 2.6 9.7 12.2 19.6
.1.6 12.2 34.4 44.0 7.7 0.7 9.2.
.. 3.1 0.9 10.4 6.2 5.1 21.7 FIT 1.49E 00 6.33E-001 1..78E 00
ENEERGY WINDOW
. 24.90 TO 2048.56.
1.00-SIGMA %ERR BKGND
" FWHM 'CHANNEL LEFT PW.
CTS/SEC %/ERR PK IT.
ENERGY AREA 24 25 26
.27
.28 29.
.30
.31
.32
.33 34
- 35 "36 37 38
- 39 40
..41 42 43
.44 45 46 47 48 49 50
.51 52
.53 54 55 56 57 58
.59*
60 011
.62 63 64
.65 0
621.60 0
630.29
.0 637.08 0
652.91
.0. 667.67 7 677.47
.7 679.90 0- 707.04.
o 722. 98 0:o 728.08 0
749.T9.
0 772.67 0 816.60 O
836.ý91 0
847.05 0
856.82 0-875.28 0
884.26 0
925.78 0
954.31 0
973.39 0 1024.33 0 1038.71 0 1072.91 0.1101.64 0 1123.98 2 1131.61 2 1136; 1 0.1237.85 0.1260.56 0 1298.36 0 1384.30 0 1398.81 0 1457.50 0 1502.24 0 1566.36 0.1596.33-
.0 1678.22 0 1706.72
.0 1791.32 0 1808.01 0 1831.43 249.
351.
355-114.
2190.
93.
76.
251.
129.
101.
469.
.1371.
.262.'
502.
1290.
203..
477..
836..
-97..
350.
136.
393.
552.
150.--
"168.
220.
1273.
165.
200.
1670.
154.
239.
88.
440.
36.
42.
552.
436.
173.
- 369, 46.
.23.
579.
595.
428.
.344.
792.
272.
291.
356.
.330.
.439.
.437.
'314.
378.
.260.,
1.83
'1243.01 1.27 1260.38 1.40
.1273.95 1.18 1305.61j 1.39 1335.12 1.21 1354.71 1.21 1359.58 1.75 1413.83 1.65.1445.71 4.73' 1455.90 1.66 1499.70
- 1.59 1545.05 1.52.1631.68 1.64. 1673.49 1.62 1693.77.
1237 1254 1269 1303 1327 1351 1351 1409 1440 1451 1494 1540 1628 1669 1685 1707 1745 1762 1843 1900.
1940 2043.
13 4.98E-01 21.8 13 7.03E-01.
15.7 10 7.10E-01 12.6 7 2.28E-01 29.8 16 4..38E 00. 3.6 13 1.85E-01 31.9 1.
13' 1.51E-01 38.9 11 5.03E-01 16.4 11 2.57E-01 28.6 14 2.03E-01 45.6 15.9.38E-01 10.7 11 2.74E 00.
3.8 11 5.24E-01.. 15..9 11 1.OOE.00 7.8
.16'2.'58E 00 4.4 13 4.06E-01.
19.4 12 9.54E-01 8.7.
13 1.67E 00 5.8 13 1.95E-01 -41.4' 16-6.99E01". 12.1 15'2.71E-01 31.6.
12 7.86E-01
.9.8.
FIT 53E 00 81E 00
.306.
1.69 286.
,1.60 306.
1.60 322*.
1.46
- 2:271.
1.95 363.
3.37 232.
1.71 323.
1.85 178.
1.63 189.
2.25 229.
.1.34 124.
1.75 127.
2.09 220.
5.48 S128..
1.81 165.
1.98
- 91.
1.68
- 69.
0.78 155.'
2.05
- 77.
1.56
- 53.
1.11
- 38.
1.97
- 42.
1..75 33..
1.52
- 11.
1.97
- 21.
2.23
.5. 0.61 1713.28
- 1750.21 1768.15 1851.17 1908.21 1946.35 2048.20 2076.96 2068 15 1.10E 00 8.3 2145.33 2139 1" 3.00E-01 20.6 2202.78"2195 17 3.35E-01 22.3 2247.44 2240 15 4.40E-01.
17.5 2262.70-2257 21 2.55E 00 3.4 1.
2271.69 2257 21.3.31E-01.19.5 2475.11 2463 "22-4.00E-01 21.5.
2520.50 2514 15 3.34E 00 2.9 2596.09M2590 13 3.08E-01 19.6 2767.91 2761 13-4i78E-01 10.5
- 2796.92 2793 10 1.76E-01 23.1 2914.27 2906 19 8.80E-01 8.4 3003.72 2996 14 7.28E-02 54.5 3131.90 3128 11 8.31E-02 36.6 3191.84 3184 17 1.10E.00.. 5.0:
3355.57 3349 14,.S.71E-01
, 5.9 3412.54 3405 16'3.46E-01 11.3 3581.69 3574 15 7.38E-01 5.9 3615.05 3606.18-9.16E-02 31.5 3661;87 3659 9 4.61E-02 33.1 PEAK SEARCH COMPLETED (REV 15.7)
$MI.
- -A
'SUMMrARY OFF NUCLIDE ACTIVITY PAGE 1:
TOTAL PEAKS IN SPECTRUM
.UNIDENTIFIED PEAKS IDENTIFIEl IN
SUMMARY
REPORT 31 34 52.31%
FISSION GAS NUCLIDE XE-131M XE-133 XE-135 XE-135M FISSION NUCLIDE TC-99M 1-131 1-132 1-133 1-134 1-135 SR-91 SR-92 Y-91M RU-106 BA-139 BA-140 LA-140 CE-141 SBHR FG FG FG FG HLIFE
- 11. 90D
- 5. 25D
- 9. 08H A15. 65M DECAY
.1.000 10001 1.014 1.617 UCI /UNIT 5.739E -4 7.835E -5 2.349E -4 3.579E -4 1.00 -SIGMA ERROR 1.176E -4 8.57?E -6.
6.013E -6
- 1.102E -5 1.00-SIGMA
%ERR 20.50 10.95 2.56 3.08 5-f c.
PRODUCT SBHR
.FP FP FP FP FP FP FP FP FP FP FP
.6.02H" 1.021 8.04D 1.001 2.30H 1.057 20.80H 1.006
- 52.60M 1.155 6.61H
.1.019 9.50H 1.013.
2.71H 1.048 49.71M 1.165 368.20D 1.000 82.71M
- 1.096 12.79D 1.000 40.22H 1.003 32.OOD 1.000
- IUCI /UNIT 1.995E -5 6.398E -4
- 2.487E. -4 1.296E -3 2.216E -4 1.220E -3 2.034E*-4
- 6.18SE -5 1.236E -4 2.509E -4 3.536E -4 1.853E -4 1.473E -4 3.788E ;-5 1.00-SIGMA ERROR 2.934E -6 1.019E -5 8.926E -6 1.191E -5 1.286E 3.537E -5 1.991E -5 6.479E -6 6.291E -6 5.4Z8E -50
- 1. 458E -5 1.934E -5 7.407E -6 4.407E -6
- 1. 00-SI GMA
%ERR
.14.71 S1. 59 3.59 0.92 5.81 2.90 9.79 10.47 5.09 21.75 4.12 10.44 5.'03 11.64
VPOTljNTIAL REPORT-Able OCCURiact oscrIiption 0t.
o vent_ /condition / Pertinent Intarortion t Itnclude-cause it'knov and corrective actions takenj On August 14",
1992 at approximately.
1330 the,condensate' demineralizer backwash receiving tank overflowed and covered the TBCCW area floor with radioactively contaminated water and resin to a level of 1-2 inches. A.sample taken from the clean sump'indicated the presence of statistically significant iodine activity. Since.
the sump pumps were on at the time, some of this activity'may'have'*
been discharged to the river. Operations was requested isolhte the./
sump pumps; absorbent. material, was *placed around the dump to" originer:
f.M prevent further contaminated material from getting into the sumpý :.
Splant c.nditions setoeting svsmt,: While an operator was backwashing the B condensate demineralizer and transfering to the condensate demineralizer backwash receiving tank, the pump 'which transfers water from the tank to radwaste
-failed.causing the backwash receivina tank to overflow.
ietificstiOem
/'isviust (Ckhbe rall block* tkat apply)
ViC.
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[
CO iVeltd J Loa'Ratty*Made I
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I Other Notified Commentt Shift.supervise:,
.1 inwt Reportable E I 36.465 lel~l)(ll
.l 1 36.34 Icl(R)
I I $6.?l (el(2)I(iv I I 30.73 (al(l)(viiil(5J"
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1 56.71 (e1(21(11
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I 20.463 4(.11i111i) 1 1 56.73 (el(21(li?
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Comments:
Comments Si g.
CAR L "
None last..
Due Date _
Alto* /
Disagree with ins teoensendatiou Comeant. /'Other Acties Desired U evonmIs copectrbae, submit copy of R'o o
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OpS.
P I
/.......
'lsmc
/
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Alp ee' a No
.22,page I ot* I t DI #91-01
. 14-AUG-92 14:20:22
- VERMONT YANKEE NUCLEAR POWER CORPORATION SAMPLE.DATE..........:
14-AUG-92 14: 05: 00' SAMPLE IDENTIFICATION:
TB 222 SPILL TYPE OF SAMPLE....
23ML.SCINT.
VIAL SAMPLE QUANTITY.....
c 23.00000 UNITS:
NL SAMPLE GEOMETRY.4.....:
VY2004 OPERATOR OR EFFICIENCY FILE NAME.:
EFF.VY2004,
-D /
", -w0ý ea.
L ACQUIRE DATE: 14-AUG-92 PRESET TIME(LIVE):
ELAPSED REAL TIME:
ELAPSED LIVE TIME:
14:11:45 500. SEC 508. SEC 500.
SEC FWHM(1332)
SENSITIVITY:
SHAPE PARAMETER NBR ITERATIONS:*
1.867 5.000 10.0 %
10.
- .3~I
- ~*********************
DETECTOR..:
20%
CALIB DATE:
14-A KEV/CHNL..:
0.50 OFFSET.... : -0.10
- 0. COEFF..:
0.00 HPGE UG-92
)01629
'59622 OE-01 00:56:04 KEV KEV/C**2 LIBRARY NUCL.LIBI ENERGY TOLERANCE 1.500KV
.* HALF LIFE RATIO 8.00 ABUNDANCE LIMIT 80.00%
- DECAY TIME*(MIN) 6.0 ENERGY WINDOW 24.90 TO
'2048.56 1.00-SIGMA %ERR PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS/SEC.%ERR FIT 1
2
.3 4
6 7
8 9
10 12 13 14 15 416 17 1i19 20 21 22 23
.0 80.30 0
140.56 0
145.55 6
162.74 6
165.88 0 :220.46 0
249.77 5
284.27 5
288.46 0
328.80 0
364.49 0
417.86 0 *423.50 0
434.28 0
487.07
.0 511.00 2
522.60 2
526.62.
2 529.92 0 537.21 0
546.52 0
555.57 0
595.47 1079.
643.
671.
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821.
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0.94.
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1.13 1654.
1.04 2262.'
1.15 2705.
1.12 1685.
A1.13 1775.
1.12 2218.
.1.00 2304..
1.19 1040.
1.21 855.
1.01 1498.
4.49 998.
1.27 2006.
2.62 414.
1.29 599.
1.43 448.
1.31 636.
1.25 464.
1.33 546..
1.30 416.
1.39 160.75 155 281.24.277 291.21 288 325,59 322 331.86 322 440.98 437.
499.59 494 568.58 562 576.94 562 657.60 654 728.94 722 835.66 832 846.94 *842 868.48 862 974.03 968 1'21.88 1014 1045.07 1042 1053.11 1042 1059.70 1042 1074.28 1069 1092.90 1088 1110.99 1105 1190.76 1186 12 2.16E 00 9 1.29E 00 7 1.34E-00
- 15. 7.44E-01 15 3.78E 00.
8 8.64E-01 11 9.57E.00 20 1.50E 00 20.1.19E.00 8-8.66E-01, 141.73E 01 11 !ýl. 13E 00 9 3.11E-01 16 4.08E-01 13 1.87E 00 19*5.74E 01 24 7.98E-01.
24 4.24E 00 24 2.64E 01 11 1.07E 00 10.1.64E 00 12 2.27E'00 10 3.87E-01
'10.9.
14.7
.11.6 20.5 4.1 19.5 2.6
-.97 12.2 19.6 1.6 12.2 34.4 144.-0
" 7.7 10.7 9.2 3.1 0.9 10.4 6.2 5.1 21.7 1.49E OC
- 6. 33E-01 1.78E 00 C. (m [ rp-)
wLf, -
PK.I T ENERGY 24 0
621.60 25 0
630.29 26 0
637.08 27 0
652.91 28 0
667.67 29 7
677.47 30 7
679.90 31 0
707.04 32 0
722.98 33 0
728.08 34 0
749.99 35 0
772.67 36 0
816.00 37 0
836.91 38 0
847.05 39 0
856.82 40 0
875.28 41.0 884.26 42.0 925.78 43 0
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973.39.
45 0 1024.33 46 0 1038.7i 47 0 1072.91 48 0 1101.64
- 49. 0 i123.98
.50 2 1131.61 51 2 1136.11 52 0 1237.85 53 0 1260.56 54 0 1298.36 55 0 1384.30 56 0.1398.81 57 0 1457.50 58 0.1502.24 59 0 1566.36
.60 0 1596.33 61 0"1678.22
.62 0 1706.72 63 0 1791.32 64 0.1808.01 65 0 1831.43 ENERGY WINDOW 24.90 TO 2048.56 1.00-SIGMA %ERR BKGND FWHM.
CHANNEL LEFT PW CTS/SEC %ERR FIT 249.
'351.
- 355.
114.
2190.
93.
76.
251 129.
101.
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262.
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.1.39 A.1.21 1.21 1.75 1.65 4.73 1.66 1.59 1.52 1.64 1.62 1.69 1.60 1.60 1.46 1.95 1243.01 1260.38 1273.95 1305.61 1335.12.
1354.71 1359.58 1413.83 1445.71
.1455.90
.1499.70 1545.05 1631.68 1673.49 1693. 77 1713.28 1750.21 1768.15 i851.17 1908.21 1237 1254 1269 1303 1327 1351 1351 1409 1440 1451 1494 1540 1628 1669 1685 1707 1745 1762 1843:
1900 3.37-.1946.35.1940" 1.71 2048'20 2043 1.85 2076.96 2068 1.63 2145.33 2139
.2.25 2202.78 2195 1."34 *2247.44 2240 1.75.2262.70 2257 2.09 2271.69 2257 5.48 2475.11 2463 1.81 2520.50 2514 1.98 2596.09 2590 1.68 2767.91 2761 0.78. 2796.92 2793 2.05`2914.27 2906 1.56 3003.72 2996 1..11 3131.90 3128 1.97 3191.84 3184 1.75 3355.57 3349 1.52*
3412.54 3405 1.97 3581.69 3574 2.23 3615.05 3606 0.61. 3661.87 3659 13 4.98E-01 21.8 13 7.03E-01 15.7 10 7.1OE-01 12.6 7 2.28E-01 29.8 16 4.38E 00 3.6 13 1.85E-*01.
31.9 1.53E OC 13 1.51E-01 38.9 11 5.03E-01 16.4 11 2.57E-01 28.6 14 2.03E-01 45.6 15 9i38E-01 10.7 11 2.74E*00 3.8 11 5.24E-01 15.9 11 1..OOE 00
- 7.8 16 2.58E 00 4.4 13 4.06E-01 19.4 12 9.54E-01 8.7.
13 1.67E 00 5.8 13 1.95E-01 41.4 16 6.99E-01 12.1 15'2.71E-01 3i.6 12 7.86E-01
.*9.8 15 1.1OE 00.
83 13 3.0OE-01 20.6 17 3.35E-01 22.3 15 4.40E-01 17.5 21 2.55E 00 3.4 1.81E OC 21 3.31E-01
.19.5 22 4. 00E-01 21.5 15 3..34E 00.
2.9 13 3.08E-01 19.6 13 4.78E-01 10.5 10 1:76E-01 23.1 19 8.80E-O1 8.4 14 7.28E-02 54.5 11 8.31E-02 36.6 17 1.10E GO 5.0 14 8.71E-01
.5.9 16z-'.46E-01 11.3 15.7.38E-01 5.9 18 9.16E-02 -31..5 9 4.61E-02 "33.1 PEAK SEARCH COMPLETED (REV 15.7)
NU.;L1lUE ILl-NIlI-IL;M1UN SY]iEMi (REV JUN 87)
SUMMARY
. OF NUCLIDE ACTIVITY PAGE 1'
TOTAL. PEAKS IN SPECTRUM UNIDENTIFIED PEAKS
.IDENTIFIED IN
SUMMARY
REPORT 65 31 34 52.31%
FISSION GAS NUCLIDE XE-131M XE-133.
XE-135 XE-135M SBHR FG.
.FG FG
'FG HLIFE
- 11. 90D 5.25D
- 9. 08H
- 15. 65M DECAY 1.S000 1.001
.1.014 1.617 UCI /UNIT 5.739E-4 7.835E -5 2.349E -4 3.579E -4 FISSION PRODUCT NUCLIDE TC-99M 1-131 I-132r 1-133 A-134 1-135 SR-91 SR-92 Y-91M RU-106 BA-139 BA-140 LA-140 CE-141 SBHR FP FP FP FP FP FP FP FP FP FP FP
.FP FP HLIFE
- 6. 02H 8.04D 2.30H
- 20. 80H
- 52. 60M
- 6. 61H
- 9. 50H 2.71H
- 49. 71M.
368. 20D 82.71M
- 12. 79D 40.22H
- 32. OOD DECAY 1.021 1.001 1.057 1.006 1.155 1.019 1'.013 1.048 1.165 1.000 1.096 1.000 1.003 1.000 UCI./UNIT 1.995E -5 6.398E -4 2.487E -4 1.296E -3 2.216E -4 1.220E -3 2.034E -4 6.18SE'-5 1.236E -4 2.509E -4 3.536E -4 1.853E -4 1.473E -4 3.78SE -5 1.00-SIGMA ERROR 1.176E -4 8.579E -6 6.013E -6 1.102E -5 1.00-SIGMA ERROR 2.934E -6 1.019E -5 8.926E -6 1.191E -5 1.286E -5 3.537E -5 1.991E -5 6.479E -6 6.291E -6 5.458E -5 1.458E -5 1.934E -5 7.407E -6 4.407E -6 1.00-SIGMA
%ERR 20.50 10.95.
2.56 3.08 1-. 00-SIGMA
%ERR 14.71 1.59 3.59 0.92
'5.81 2.90 9.79 10.47 5.09 21.75 4.12 10.44 5.03 11.64 1.
14-AUG-92 1.4:29:56 VERMONT YANKEE NUCLEAR POWER CORPORATION SAMPLE DATE..........
14-AUG-92 14:10:00 SAMPLE IDENTIFICATION:
TB CLEAN SUMP TYPE OF SAMPLE....... :
LIQUID MARINELLI SAMPLE QUANTITY...... :
1000.000 UNITS:
ML SAMPLE GEOMETRY*.....
VY2005 OPERATOR..............
SCM EFFICIENCY FILE NAME.:
EFF.VY2005*,
ACQUIRE DATE: 14-AUG-92.14:24:21
- FWHM(1332) 1.867 PRESET TIME(LIVE):
.2000.
SEC
- SENSITIVITY:
5.000 ELAPSED REAL TIME:
326. SEC SHAPE PARAMETER.: 10.0 %
ELAPSED LIVE TIME:
326. SEC
- NBR ITERATIONS:
10.
I ýý-t,-f1 DETECTOR..:
20% HPGE
- LIBRARY NUCL.LIB1 CALIB DATE:
14-AUG-92 00:56:29
- .ENERGY TOLERANCE 1.500KV.
KEV/CHNL...:
0.5001629
- HALF LIFE RATIO 8.00 OFFSET.... : -0.1059622 KEV
- ABUNDANCE.LIMIT 80.00%,
Q.
COEFF;.:
O.OOOE-01 KEV/C**2
- DECAY TIME (MIN) 14.0 ENERGY WINDOW 24.90 TO.2048.56 1.00-SIGMA %ERR PK-IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS/SEC %ERR FIT
.1 23 45 6
78
.9 10 11
.0 0
0 0
0O 0
.0
-0 0
0 O,
249.61 364.48 489.82 511.06.
529.93 667.92 772.51 846.74 884.87 1131.80 1260.39.
39.
132.
7.
625. "
204.
39.
27.
19.
.13..
14.
36.
31.
30o.
71.
8.-
13.
4.
2.
4.
"0.
16.
0.
1.71 1.21 1,15 2.57 1.34 2.34 1.32 1.00 1.16.
0.71 0.77 499.26 497 728.93 724 979.53 978 1022.00 1014 1059.73 1056 1335.62 1327 1544.72 1538 1693.15.1690 1769.38.1764 2263.07 2253 2520.17 2511 6 1.21E-01 10 4.05E-01 6 2.07E-02 18 1.92E 09 9 6.27E-01 16 1.19E-01 12 8.37E-02 8 5.68E-02 12 3.99E-02 13 4.25E-02 18*1.10E-01 29.0 12.1 89.5 4.3 8.2 19.7 25.1 30.1
.27.7 56.7 20.8 PEAK SEARCH.COMPLETED (REV. 15.7)
N:.2'LIDE IDENTIFICATION SYSTEM (REV JUN 87)
SL:IMMRY OF NUCLIDE ACTIVITY PAGE 1
fOTAL PEAKS IN SPECTRUM UNIDENTIFIED PEAKS 1DENTIFIED IN
SUMMARY
REPORT.
11 4
7 63.64%
FISSION GAS NUCLIDE SBHR XE-135 FG FISSION PRODUCT NUCL IDE SBHR 1-131 FP 1-133 FP 1-134 FP 1-135 FP HLIFE DECAY
.9.'08H 1.022 UCI /UNIT 1.914E -7 UCI /UNIT 8.944E -7 1.761E -6
- R3.045E -7 2.127E -6 1.00-SIGMA ERROR
- 5. 553E -
1.00-SIGMA ERROR 1.084E -7
.1.436E -7 8.445E -8 4.432E -7 1.00-SIGMA
%ERR 29.01
- 1. 00-SIGMA
%ERR 12.12.
8.15 27.73 20.83 HLIFE 8.04D 20.80H
- 52. 60M 6.61k1 DECAY 1.001 1.010 1.252 1.030
- 1.
4
S**:,
-x**~
14-AUG-92 15:01: 15 VERMONT YANKEE NUCLEAR POWER CORPORATION SAMPLE DATE..........
14-AUG-92 14:10:00
\\
SAMPLE IDENTIFICATION:
LIQUID MARINELLI coL*
SAMPLE QUANTITY......
i000.000 UNITS:
ML SAMPLE GEOMETRY......
VY2005 OPERATOR.............
sCMq EFFICIENCY FILE NAME.:
EFF.VY2005 7, ACQUIRE DATE: 14-AUG-92 14:24:21 PRESET TIME(LIVE):
2000.
SEC ELAPSED REAL TIME:
2001.
SEC ELAPSED LIVE TIME:
2000. SEC FWHM(1332)
SENSITIVITY:
SHAPE PARAMETER NBR ITERATIONS:
1.867 5.000 i0.0 %
i0.
DETECTOR..:
20% HPGE
- LIBRARY NUCL.LIB1 CALIB DATE:
14-AUO-92 00:56:29
- ENERGY TOLERANCE 1.500KV KEV/CHNL..:
0.5001629
- HALF LIFE RATIO 8.00 OFFSET.... : -0.1059622 KEV
- ABUNDANCE LIMIT 80.00%
Q. COEFF..:
O.OOOE-01 KEV/C**2
- DECAY TIME (MIN) 14.0 ENERGY WINDOW 24.90 TO 2048.56 I.00-SIGMA %ERR PK IT ENERGY AREA BKGND FWHN CHANNEL LEFT PW CTS/SEC %ERR FIT i
4 6
7 8
10 i 1 12 13 14 15 16 17 18 19 21 22 23 249.91 284.07 364.45 417.86 511.04 526.51 529.91 546.81 637.41 667.81 772.69 836.86 847.23 875.46 884.18 953.9?
1038.59 1131.46 126 0.30 1298.49 1457.57 1677.60 1790.53 264.
71.
d 2."
86.
3455.
158.
1239.
84.
37.
240.
146.
53.
61.
58.
62.
30.
76.
132.
195.
13.
80.
50.
42.
425.
228.
167.
i25.
168.
54.
45.
43.
38.
37.
16.
18.
52.
18.
19.
18.
26.
9.4.
9.
0.
0.
4.
1.21 1.45 1.26 1.11 2.53 1.53 1 33 1.49 1.27 1.53 1.75 2.11 1.13
- i. 32
- 1. 01 1.74 1.87 1.70 1.51 1.42 2.44 1.86 1.75 499.87 568.17 728.88 835.67 1021.96 1052.88 1059.68 1093.49 1274.62 1335.40 1545.09 1673.38 1694.12 1750.57 1768.00 1907.56 2076.71 2262.40 2519.99 2596.36 2914.40 3354.32 3580.10 494 565 724 829 1014 1049 1049 1089 1268 1329 1538 1668 1687 1743 1763 1902 2069 2258 2511 2592 2905 3348 3573 12 8
9 12 22 17 17 10 15 13 11 14 15 11 11 17 10 18 10 22 15 13 1.32E-01 17.3 3.56E-02 40.7 4.13E-01 4.6 4,28E-02 30.0 1.73E 00 2.0 7.88E-02 10.8 6.19E-01 3.0 4.20E-02 20.2 1.86E-02 38.0 1.20E-01 9.0 7.28E-02 11.5 2.65E-02 24.3
- 3. 03E-02.27.2 2.90E-02 %20.8 3.08E-02 120.8 1.50E-02 40.4 3.80E-02 20.6.
6.58E-02 10.1 9.73E-02 8.0 6.52E-03 52.6 4.OOE-02 13.1 2.50E-02 14.1 2.11E-02 19.4
- 1. 36E O(
PEAK* SEARCH COMPLETED (REV 15.7) 4
NUCLIDE IDENTIFICATION SYSTEM (REV JUN 87)
SUNM.1ARY'OF NUCLIDE ACTIVITY PAGE 1
TOTAL PEAKS IN SPECTRUM UNIDENTIFIED PEAKS 1DENTIFIED IN
SUMMARY
REPORT 14 60O.87%
FISSION GAS NUCLIDE SDHR XE-135 FC XE-1335M FG FISSION PRODUCT HLIFE DECAY 9.08H 1.040 15.65M 3.614 UCI /UNIT
- 2. 131E -7 8.495E -7 1.00-SIGMA ERROR 3.690E -8 9.141E -8 1,00-SIGMA
%ERR 17.32 10.76 NUCLIDE 1-131 1-132 1-133 1-134 1-135 SBHR FP FP FP FP FP HLIFE DECAY 8.04D 1.002 2.30H 1.167 20.80H 1.017 52.60M 1.493 6.61H 1.056 UCI /UNIT
- 9. 131E -7 4.189E -7 1.753E. -6 2.799E -7.
1.920E -6 1.00-SIGMA ERROR 4.185E -8 3.750E -8 5.285E -8 5.830E -8 1.527E -7
- 1. 00-SIGMA
%ERR 4.58 8.95 3.02 20.83 7.96 4
-1 1s IoI I..
1 00 lot 1 3 111 1
-1P10 101 t 2 IC o
101 b
-o' CPS LOG I i 9 1111i 0cr 10 01o '
12 o3 1o4 1101 to.
cbps Aoc I
I II I *I
'* ti.
JbI ILb Vt I.
f.
A ~********4A-****
4~******
- 14-AUG-9214020:56 VERMONT YANKEE NUCLEAR POWER CORPORATION I
SAMPLE DATE SAMPLE IDENTIFICATION:
TYPE OF SAMPLE.......
SAMPLE QUANTITY......
SAMPLE GEOMETRY,....
OPERATOR.............
EFFICIENCY FILE NAME.:
14-AUG-92 14:10:00
.TB CLEAN SUMP LIQUID MARINELLI 1000.000 UNITS:
ML VY2005 SCM EFF. VY2005,,
glo 31~a(Q ACQUIRE DATEY 14-AUG-92 14:24:21
- FWHM(1332) 1.867 PRESET TIME(AIVE):
2000. SEC
- SENSITIVITY:
5.000 ELAPSED REAL :T IME:
326. SEC
- SHAPE PARAMETER
- 10.0 %
ELAPSED LIVE TIME:
326.,SEC
- NBR ITERATIONS:
10.
DETECTOR..:
20% HPGE
- LIBRARY NUCL.LIB!
CALIB DATE:
14-AUG-92 00:56:29
- ENERGY TOLERANCE 1.500KV KEV/CHNL..:
0.5001629
- HALF LIFE RATIO
.040 OFFSET....: -0.1059622 KEV
- ABUNDANCE LIMIT 80.00%
- 0. COEFF..:
O.O00E-01 KEV/C**2
- DECAY TIME (MIN) 14.0 ENERGY WINDOW 24.90 TO 2048.56 1.00-SIGMA %ERR PK IT ENERGY 1
0 249.61 2
0 364.4S 2
0 489.S2 4
0 511.06 5
0 529.93 6
0 667.92 7
0 772.51 8
0 846.74
?
0 354.87 10 0 1131.80 11 0 1260.39 AREA DKGND FWHM CHANNEL LEFT PW CTS/SEC %ERR FIT 39.
132.
7.
- 625, 204.
37.
27.
19.
13.
14.
36.
Si.
30.
7.
1.
13.
4.
2.
4.
0.
16.
0.
1.71 1.,15 2.57 1.34 2.34 1.32 1.00 1.16 0.71 0.77 499.26 728.93 979.53 1022.00 1059.73 1335.62 1544.72 1693.15 1769.38 2263.07 2520.17 497 724 978 1014 1056 1327 1538 1690 1764 2253 2511 6
10 6
18 9
16 12 8
12 13 18
- 1. 21E-01
- 4. 05E-0 1
- 2. 07E-02 1.92E 00 6.27E-01
- 1. 19E-01
- 8. 37E-02
- 5. 68E-02
- 3. 99E-02 4.25E-0r2
- 1.
OE-Ol 29.0 12.1 89.5
- 4. 3 8.2 19.7 25.1
- 30. 1 27.7 56.7 20.8 PEAK SEARCH COMPLETED (REV 15.7)
NUCLIDE IDENTIFICATION SYSTEM (REV JUN 87)
SUMMARY
OF NUCLIDE ACTIVITY PAGE 1
TOTAL PEAKS IN SPECTRUM UNIDENTIFIPD PEAKS IDENTIFIED IN
SUMMARY
REPORT 11 4
7 63.64%
FISSION GAS NUCLIDE SBHR XE-135 FO FISSION PRODUCT HLIFE DECAY UCI /UNIT 9.08H 1.022 1.914E -7 1.00-SIGMA ERROR 5.553E -8 I.O0-SIGMA
%ERR 29.01 NUCLIDE 1-131 1-133 1-134 1-135 SEBHR FP FP FP HLIFE
- 8. 04D
- 20. SOH
- 52. 60M 6.61H DECAY 1.001 1.010 1.252 1.030 UCI /UNIT 8.944E -7 1.761E -6 3.045E -7 2.127E -6 1.00-SIGMA ERROR 1.084E -7 1.436E -7 8.445E -8 4.432E -7 1.00-SIGMA
%ERR 12.12 8.15 27.73 20.83
3
+/-4-AUG-92 14:20:224 VERMONT YANKEE NUCLEAR POWER CORPORATION r
SAMPLE DATE...........
14-AUG-92 14:05:00 SAMPLE IDENTIFICATION:
TB 222 SPILL TYPE OF SAMPLE.......
23ML SCINT.
VIAL SAMPLE QUANTITY 23.00000 UNITS:
ML SAMPLE GEOMETRY......
VY2004 OPERATOR..............
OR EFFICIENCY FILE NAME.:
EFF.VY2004,7 J-, 41Ioo, ek 6v ACQUIRE DATE; 14-AUG-92 PRESET TIME(IbVE):
ELAPSED REAL iIME:
ELAPSED LIVE tIME:
14:11:45 500. SEC 508. SEC 500. SEC FWHM( 1332)
SENSITIVITY:
SHAPE PARAMETER NBR ITERATIONS:
1.867 5.000 10.0 0
10.
DETECTOR..:
20% HPGE
- LIBRARY NUCL.LIB1 CALlIB DATE:
14-AUG-92 00:56:04
- ENERGY TOLERANCE 1Q500KV KEV/CHNL.:
0.5001629
- HALF LIFE RATIO 8.00 OFFSET....: -0.1059622 KEV
- ABUNDANCE LIMIT 80.00%
Q.
COEFF..:
O.O00E-01 KEV/C**2 DECAY TIME (MIN) 6.0 ENERGY WINDOW 244.90 TO 2048.56 1.00-SIGMA %ERR PK IT ENERGY AREA BKGND " FWHM CHANNEL LEFT PW CTS/SEC %ERR FIT A
2 4
5 6
7 C
7 10 1i 12 13 14
+/-5 16 17 19 20 21 2?
0 0
0 6
6 0
05 5
0 0
0 0
0 0
0 2
2 0
00 0
80.30 140.56 145.55 162.74 165.88 220.46 249.77 284.27 288.46 328'. 80 364.49 417.86 423.50 4344.28 487.07 511.00 522.60 526.62 529.92 537.21 546.52 S55.57 595. 47 1079.
6143.
671.
.372.
1891.
432.
4786.
752.
596.
4 3.
8637.
563.
156.
204a 933.
28700.
399.
2118.
13207.
537.
821.
1134.
194.
3 153.
2543.
1928.
1985.
1654.
2262.
2705.
1685.
1775.
2218.
2304.
1040.
855.
1498.
998.
2006.
414.
599.
448.
636.
464.
546.
416.
1.52 0.94 1.13
+/-1.13 1.04 1.15 1.12 1.18 1.12 1.00
- 1. i9 1.19 1.01 4.49 1.27 2.62 1.29 1.43
- 1. 3 1.25 1.31 1.30 1.39 160.75 26 1. 24 291.21 32'5. 59 331.86 440.98 499.59 568.58 576.94 657.60 728.94 835.66 846.94 868.48 974.03 1021.88 1045.07 1053. 11 1059.70 1074.28 1092.90 1110.99 1190.76 155 277 322 437 494 562 654 722 632 842 662 968 1014 1042 1042 1042 1069 1088 1105 1186 12 9
7 L15
-5 8
11 20 20 C
14 11 16 13 19 24 24 24 11 10 12 i0
- 2. 16E 00 1.29E 00 1.34E 00
- 7. 44E-01 3.78E 00 8.64E-01 9.57E 00 1.50E 00 1.19E 00
- 8. 66E-01 1.73E 01 1.13E 00
- 3. 1 IE-O0 4.O8E-01 1.67E 00 5.74E 01
- 7. 98E-01 4.24E 00 2.64E 01 1.07E 00 1.64E 00 2.27E 00
- 3. 87E-01 10.9 14.7 11.6 20.5 4.1 1.5 2.6 9.7 12.2 19.6 1.6 12.2 34.4 44.0 7.7 0.7 9.2 3.1 0.9 10.4 6.2 5.1
-21.7 1.4S'E n-00 6.33E-01
- 1. 76E 00
ENERGY WINDOW 24.90 TO 2048.56 lO0-SIGMIA %ERR PK I T ENERGY 24 45 2Co%
27 340 31 32 33 34 3.5 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50
-51
,52 53 54
ý55 56 57
~5.9 60C 61 62 63 64 65 621.60 630.29 637.08 652.91 667.67 677.47 679.90 707.04 722.98 728.08 749. ý9 772.67 816. 00 83,.91 847. 05 856.82 875.2-8 884.26 925.78 954.31 973.39 1024.33 1038.71 1072.91 1101.64
- i -Z3.9 8 1131.61 1136.11 1-237.85 1260.56 1298.36 1384. so 1398.81 1457.50 1502.24 1566.36 1596. 33 1678.22 1706.72 1791.32 1808.*01 1831.43 AREA 249.
35 1.
S-55.
114.
2190.
76.
- 25..
129.
101.
469.
1371.
262.
502.
1290.
203.
477.
836.
97.
350.
136.
.Lý.C.
55-.4.
150.
168.
1273.
165.
200.
1670.
154.
239.
88.
440.
42.
552.
436.
173.
369.
46.
23.
BKGND FWHM CHAiNEL LEFT 579.
595.
428.
344.
792.
272.
291.
356.
330.
439.
437.
314.
378.
260.
365.
306.
286.
306.
3.-4-4 271.
363.
2 3 2.
178.
189.
229.
124.
127.
220.
165.
91.
69.
155.
77.
53.
38.
33.
ii.
21.
5.
- 1. 83 1.27 1.40 1.18 1.39 1.21 1.21 1.75 1.65 4.73
- 1. 6L'.
1.59
- 1. 52 1.64 1.62 1.69 1.60 1i. 60 1.46 1.95 3.37 1.71 1.85 1.63 2.25 1.34 1.75 2.09 5.48 1.81 1.98
- i. 68 0.78
- 2. 0-5, 1.56 1.11 1 97 175 1.52 1.97 2.23 0.61 1243.01 1260.38 1273.95 1305.61 1335. 12+/-
1354.71 135-9. 58 1413.83 1445.71 1455.90 1499.70 1545.05 1631.68 1673.49 1693.77 1713.28 1750.21 1768.15 1851.17 1908.21 1946.35 2048.20 2076.96 2145.33 2202. 7/8 2247.44 2262.70 2271.69 2475.11 2520.50 2596.09 2767.91 2796.92 2914.27 3003.72 d13.d90 3191.84 3355.57 3412.54 3531.69 3615.05 3661.87 FW CTS/SEC %ERR 1237 1254 1269 1303 1327 1351 1351 1409 1440 1451 1494 1540 1628 1669 1685 1707 1745 1762 1843 1900 1940 2043 2068 2i39 2195 2240 2257 2257 2463 2514 2590 2761 2793 2906 2996 3128 3184 3349 3405 3574 3606 3659 13 4.98E-01 13 7.03E-01 10 7. 10E-01 7 2.28E-01 16 4.38E 00 13 1.0-5E-01 13 1.51E-01 11 5.03E-01 11 2.57E-01 14 2.03E-01 15 9.38E-01 11 2.74E 00 11 5.24E-01 11 1.OOE 00 16 2.58E 00 13 4.06E-01 12 9.54E-01 13 1.67E V0 13 1.95E-01 16 6.99E-01
- 15 2.71E-01 12 7.86E-01 15 1.1OE 00 13 3.00E-01 17 3.35E-01 15 4.40E-01 21 2.55E 00 2'1 3.31E-01
-2 4.OOE-01 15 3.34E 00 13 3.08E-01 13 4.78E-01 10 1.76E-01 19 8.80E-01 14 7.28E-02 11 8.31E-02 17 1.1OE 00 14 8.71E-01 16 3.46E-01 15 7.33E-01 18 9.16E-02 9 4.61E-02 21.8 15.7 12.6 29.8 3.6 31.9 38.9 16.4 28.6 45.6 10.7 Zn 6-15.9 7.8 4.4 19.4 8.7 5.8 41.4
- 12. 1 31.6 7.8 S.,3 20.6 22.3 17.5 3.4 i?. 5 21.5 19.6
- 23. 1 8.4 54.5 136.6 5.0 5.9 11,3 5.9 31.5 33.- 1 FIT
- 1. 53E 00 PEAK SEARCH COMPLETED (REV 15.7)
SULMgARY OF NUCLIDE ACTIVITY TOTAL PEAKS IN SPECTRUM 65 UNIDENTIFIED PEAKS 31 IDENTIFIER IN
SUMMARY
REPORT 34 52.31%
PAGE 1
FISSION GAS
'C.-
NUCL IDE XE-J 31N XE-133 XE-135 XE-135M FISSION NUCL IDE TC-99M 1-131 1-132 1-133 1134 I. -
L 3D 5 1-135 SR-91 SR-92 Y-91M1 RU-i06 BA--139 BA-140 LA_-140 CE-141 SBHR FG FG FG HLIFE
- 11. 90D
- 5. 25D
- 9. 08H
- 15. 65M DECAY 1.000 1.001 1.014 1.617 UCI /UNIT 5.739E -4 7.835E -5 2.349E -4 3.579E -4 PRODUCT SBHR FP FP FP FP FP FP FP nr F P FP FP FP FP FP HLIFE
- 6. 02H S.04D 2.30H
- 20. 80H
- 52. 60M 6.61 H 9 *50H 71H
- 49. 71M 368.20D 82.71M
- 12. 79D 40.22H 32.00D DECAY 1.021 1.001 1.057
- 1. 006 1.155 1.019 1.013 1.048 1.165 1.000 1.096 1.000
- 1. 003
- 1. 000 UCI /UNIT 1.995E -5 6.398E -4 2.487E -4 1.296E -3 2.216E -4 1.220E -3 2.034E -4
- 6. 188E -5 1.236E -4 2.509E -4 3.536E -4
- 1. 853E -4 1.473E -4 3.788E -5 1.00-SIGMA ERROR 1.176E -4 S. 57E -6 6.013E -6 1.102E -5 1.00-SIGMA ERROR 2.934E -6 1.019E -5 8.926E -6 1.191E -5 1.286E -5 3.537E -5 1.991E -5 6.479E -6 6.291E -6 5.458E -5 1.458E -5 1.934E -5 7.407E -6 4.407E -6 1. 00-SIGMA
%ERR 20.50 10.95 2.r.56 3.08 1.00-SIGMA
%ERR 14.71 1.59 3.59 0.92 5.81 2.90 9.79 i0.47 5.09 21.75 4.12 10.44
- 5. 03 11.64
17-AUG-72 14:43:10 VERMONT YPNKEE NUCLEAR POWER CORPORATION SAMPLE DATE.;........
17-AUG-92*i.:0:00 SAMPLE IDENTIFICATION:
TB SUMP fLD TYPE OF SAMPLE....... :
LIQUID MA'INELLI SAMPLE QUANTITY......
i000.000 UNITS:
ML SAMPLE GEOMETRY......
- VY2005 OPERATOR...............
SCM EFFICIENCY FILE NAME.:
EFF.VY2005 7 7 ACQUIRE DATEJ 17-AUG-92 14 09:38
- FWHM(1332) 1.845 PRESET TIME(LIVE):
2000. SEC
- SENSITIVITY:
5.000 ELAPSED REALOJIME:
2002.
SEC
- SHAPE PARAMETER : 10.0 %
ELAPSED LIVE TIME:
2000. SEC
- NBR ITERATIONS:
10.
DETECTOR..:
20% HPGE
- LIBRARY NUCL.LIBl CALIB DATE:
17-AUG-92 00:27:05
- ENERGY TOLERANCE 1.500KV KEV/CHNL..:
0.5001556
- HALF LIFE RATIO 8.00 OFFSET.... : -0.1080463 KEV
- ABUNDANCE LIMIT 80.00%
Q.
COEFF..:
O.OOOE-01 KEV/C**2
- DECAY TIME (MIN) 9.0 ENERGY WINDOW 24.90 TO 2048.53 1.00-SIGMA %ERR PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS/SEC %ERR FIT 1
4 5
6 7
10 10 12 i3 14 15 16 17 19 20 21 22
.23 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 00 80.69 141. 18 145.45 162.48 249.92 284.39 304.71 328.80 364.49 423.81 432.38 438.21 487.03 510.50 529.91 537.27 636.96 722.91 751. 52 815.79 857.56 867.86 875.13 2549.
150.
912.
475.
169.
1336.
149.
894.
14625.
120.
91.
56.
1438.
79.
2326.
700.
836.
185.
113.
568.
26.
137.
91.
1459.
1617.
1028.
1522.
577.
545.
430.
382.
396.
127.
162.
- 150, 113.
73.
137.
98.
54.
46.
35.
41.
57.
21.
21.
1. 44 2.32 1.09 1.11 1.11 1.15
- i. 19 1.10 1.22 1.18 0.76 0.97 1.34 1.79 1.30 1.41 1.43 1.21 1.32 1.79 3.58 1.28 1.52 161.55 282.48 291.03 325.08 499.91 568.82 609.44 657.60 728.96 847.58 864.70 876.37 973.97 1020.90 1059.72 1074.41 1273.74 1445.59 1502.79 1631.29 1714.81 1735.39 156 276 288 321 496 564 606 654 723 844 859 872 968 1017 1053 1067 1266 1442 1497 1624 1709 1730 10 1.27E 00 11 7.50E-02 7 4.56E-01 9 2.38E-01 8 8. 43E-02 11 6.68E-01 8 7.43E-02 8 4.47E-01 13 7.31E 00 9 5.99E-02 11 4.53E-02 10 2.79E-02 14 7.19E-01 9 3.97E-02 13 1.16E 00 15 3.50E-01 13 4.18E-01 10 9.27E-02 11 5.65E-02 15 2.84E-01 19 1.30E-02 12 6.87E-02 14 4.55E-02 3.5 53.1 6.8 16.0 26.0 4.5 26.3 5.2 0.9 20.2 30.9 44.6 3.1 26.7 2.3 4.9 4.0 10.9 161.
5.0 81.0 12.9 15.9 1749.93'1742
PK IT ENERGY 24 0
919.38 25 0
925.31 26 0 1596.12 AR 1
P ENERGY WINDOW 24.90 TO 2048.53 1.00-SIGMA %ERR EA BKGND FWHM CHANNEL LEFT
- 63.
- 22.
1.38 1838.41 1831
- 80.
- 16.
1.47 1850.26 1844
- 04.
- 15.
2.18 3191.47 3183
'EAK SEARCH COMPLETED (REV 15.7)
PW CTS/SEC %ERR 13 3.13E-02 21.4 14 8.99E-02 9.3 19 5.52E-01 3.1 FIT
NUCLIDE IDENTIFICATION SYSTEM (REV JUN. 87)
SUMMARY
OF NUCLIDE ACTIVITY PAGE 1
TOTAL PEAKS IN SPECTRUM UNIDENTIFIFD PEAKS IDENTIFIED IN
SUMMARY
REPORT 26 8
18 69.23%
FISSION GAS NUCLIDE XE-131M XE-1S3 XE-135 SBHR FG FG FG HLIFE
- 11. 90D 5.20D
- 9. 08H DECAY 1.001 1.002 1.034 UCI /UNIT 1.151E -5 3.511E -6 1.352E -7
- i. 00-SIGMA ERROR 1.839E -6 1.217E -7 3.519E -8 1.00-SIGMA ERROR 2.765E -8 I.00-SIGMA
%ERR 15.98 3.47 26.03 1.00-SIGMA
%ERR 44.56 ACTIVATION PRODUCT.
NUCLIDE SBHR HL ZN-69M AP H
FISSION PRODUCT
.IFE DECAY UCI /UNIT
,.80H 1.022 6.205E -8 NUCLIDE TC-99M 1-131 1-133 BA-140 LA-140 CE-141 SBHR FP FP FP FP FP FP HLIFE
- 6. 02H S. 04D
- 20. 80H
- 12. 79D
- 40. 22H
- 32. GOD DECAY 1.052 1.002 1.015 1.001
- 1. 008 1.000 UCI /UNIT 8
07E -e 1.616E -5
- 3. 282E -6 3.445E -6 3.826E -6 8.469E -7 1.00-SIGMA ERROR 4.249E -8 1.423E -7 7.609E -8 1.678E -7' 1.182E -7 5.718E -8 1.00-SIGMA
%ERR 53.06 0.88 2.32 4.87 3.09 6.75 VERMONT YANKEE QUANTITATIVE RADIOISOTOPIC LLD ANALYSIS 17 AUG 1992 14:46:48 LIQUID SAMPLE
- NEXT TO LLD LIMIT INDICATES LLD NOT MET NUCLIDE LLD UCI/ML LLD LIMIT UCI/ML XE-133 3.745E-07 XE-133M 7.360E-07 XE-135 9.533E-08 XE-138 3.637E-07
- 1. OE-05 1.OE-05 1.OE-05 1.OE-05 1.OE-05 1.OE-05
- 5. OE-07 ISOTOPE POSITIVELY IDENTIFIED ****
- ISOTOPE POSITIVELY IDENTIFIED ****
KR-87
- 1. 173E-07
- 4. 928E-08
MO-??
FE-59 CO-58 CO-60 ZN-65 I1-131 CS-134 CS--137 CE-141 CE-144 3.9?22-E-07
- 1. 143E--07
'5.
024E-08 1-013E-07
- 1. 43 1E-07
- 6. 245E-07
- 5. 400E-08
- 6. 142E-07
- 5. OE" 07
- 5. OE-07
- 5. OE-07
- 5. OE-07
- 5. OE-07
- 1. OE-06
- 5. OE- 07
- 5. OE-07
- 5. OE-07
- 5. OE-07 ISOTOPE POSITIVELY IDENTIFIED ISOTOPE POSITIVELY IDENTIFIED
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- r. 0,19-i1 Attachment, VYNPC, 8/20/92 D
'~ P' K
Overflow of Condensate Demineralizer Backwash Receiving Tank On August 14, 1992 at approximately 1330, while backwashing the B condensate demineralizer and transferring the contents to the condensate demineralizer backwash tank, the electric pump which transfers the water from the tank to radwaste failed, reyilt>. in the backwash receiving tank overflowing onto the floor. The water was radioactively contaminated and contained some resin material
-e floor in the vicinity of the tank was flo,'Y-.d to a depth of approximately 1-2 inches.
Samples taken in ý ::earby sump indicated the presence of..,z.ioctive Iodine and Tritium.
The sump purrqps are designed to cycle if required by level so it is possible that some contaminated water was discharged to the river by way of the service water system (10,000 gpm) and'then into the main circulating water system (360,000 gpm) before entering the Connecticut River.
The precise volume of contaminated water that may have been discharged to the river is estimated to be less than 15 gallons. Radiation monitors and samples at
- irt (if discharge did r," record any evidence of radioactivity and remained normal durn.
-e personnel isolated the sump pumps and terminated the poti-.ntial 6,,..arge at
- v 1430.
,ical analysis of samples taken from the floor, sumps, and the discharge suming bounding conditions, Vermont Yankee calculated that Technical
-..i NRC 10CFR requirements and limits were not exceeded and the event was t re:
the NRC. The calculated parameter values were also below :.-mont Aealth Radiological Health limits and the NPDES Permit limits.
"T'..
.ed values were based on the extremely conservative assumption.that rat.
wate.
o pumped out of the sumps and discharged through the normal flow path"to th%.;... r continuously during the event. The calculation assumes dilution by the flow of the Circulating Water system (360,000 gpm) occurring concurrently with the discharge.
The actual volume of radioactive water discharged is estimated to be three orders *.. magnitude below the bounding calculated values, or less than 15 gallons. Connecticut Rive: flowat the time of the incident was approximately 6000 cf-DJM.8/20/92 TrnT0l P S71
SUIiMARY OF APPLICABLE LIMITS AND "OUTER BOUNDS" CALCULATED VALUES FOR LIQUID RELEASE OF 8/14/92 Bases -
The "Calculated Value is based upon the assumption that".
12000 gallons of radioactive water was pumped out -of the. TB Clean*
Sump and discharged, through the normal flow path,.to the river.
The calculation assumes dilution by the.. flow.of. 'Circulating Water(360000 gpm) occurring concurrently with this disicharge..:...,.*
APPLICABLE LIMITS
.LIQUID
-RELEASE E IIC'I "
alculaite alue "
TECHINICAL SPECIFICATIONS
.jiquid.Effluents: Concentrations 1)T.S.3.8.A.1 S
1 MPC as determined" by 10CFR20, App.B, Table II, Col. 2
" conc. (Noble Gases excluded).
2.92E-*3 MPCs's 2)T.S.3.8.A.1 -'Total Noble.Gases Conc.
e 2E-4 uci/cc 1.16E-9 uci/cc Liquid Effluents: Dose 1)Total Body.Dose -T.S.3.8.B.1 1.5 mrem in any quarter,-
3 mrem total for year 2)Organ Dose -. T.S.3.8.B.I -
5 mrem in any quarter, I El rn 4-.4.-
1 4-
-.-W L.L 1.52E-6 mrem 7.47E-4 mrem' 2.92E-3 MPC's' LL 1=4*u U %J G.L U.IW.L _y z
C 10CFR50.72 REPORTING REQUIREMENTS 2 times MPC when averaged over one hour NPDES REPORTING REQUIREMENTS Unplanned. Releases Yes 10CFR20 App B, Table II, Coi.2.
'.2-As 1
'M :
2.92E-3 14PC's
.(
1 MPC)
MPC.
Total*Radionuclides(excluding tritium)..:'..'.....
shall be _
5 curies per year 4.42E-4 curies Total Tritium shall be < 5 curies per year.
4.82E-4 'curies"..
Dose Calendar quarter -
< 1.5 mren total*'body
';52E-6' mrex 5 5 mr.m to'any organ 7.47E-4* mrem`"?* :"..
Calendar year
< 3 mrem total body.
.52E-6 mrem."
< 10 mrem to any organ*,.
.7.,47E;-4 mrem.
pH -
6.5 to 8.5 Standard Units
- w.:-
- 7.6 Flow 14.4 million gallons per day
- 12000 gallon.
VERMONT STATE RAD HEALTH REGULATIONS(Part 5, Chap. 3)
- 1. Radioactive.Material(except tritium and dissolved noble gases S 1E-7 uci/m14 Additional action levels4
>2% of IE-7(or 2E-9)uci/ml*...
Requires investigation, programs to reduce-releases and report to Vt.. Board of Health within 14 days (see regulation for additional details)
>4% of 1E-7(or 4E-9)uci/m14 Requires investigation, immediate report to the Vt. Board of Health and then, < 14days later, followup. report to Vt. Board of.
Health(see regulation for additional details)'
- 2. Tritium -
< 3E-3 uci/ml (see regulation for additional quarterly
~limits) 4.1IOE-*9 uci/rnl.
- 4. IOE-9 uci/ml 4.10E-9 uci/ml 5.72E-9 UCi/ml 30 Dissolved noble gases -I 4E-5 uci'/ml 1.16E-9 uci/ml (see regulation for additional quarterly limits) v-A 6j4,wj4~~ ~~~
~eY-
ýee-eo
IF:.
ALARM RESPONSE SHEET PROCESS RADIATION MONITORING 3-F-6 Page 1 of 1 SERVICE WATER Rev.
3 FFLUENT RAD HI uses:
Setpoints:
Actuating Devices:
- .-High background radiation 5.1 cps
- 1. RM-17-351
'lAevels.
References:
CWD 983 ON 3153 Conf irmation:
- 1. Service water rad monitor reading on RR-17-353 on CRP 9-2.
Service water rad monitor RM-17-351 on CRP 9-10.
Automatiqc. Actions:
None rator Actions:
- 1.
Verify radiation level is high in the service watersystem.
- 2.
Check service-water and rad. monitor lineup.
- 3.
Check for high background area radiation near service water 4,
rad. monitor.
- 4. Refer to ON 3153.
- I
- I
- 1 I'
ii i** 1 I
I.
- I
- 1t I.
f MEMORANDUM To: Van Bowman
. Vernon Augustl20, 1992
.rrom:
stv skb.os ernonLU..
Subject:
Analysis of Station Air Compressor Blowdowh to* d6termine Appropriate Flow Pathway
Attachment:
Memo from Steve McAvoy to Steve Skibniowsky,
. dated August*20,
" AS a*f0low up to our discussion concerning the appropriate fl67 pathway *for blowdown of condensed water from the Station Air S.
Compressor, I have evaluated the attached memo from Steve McAvoy
.'concerning the analysis of some of the input sources to the TB Clean..Sump.
I have 'concluded -that, given the
.. radion'iilides identified in the compressor blowdown sample, the only appropriate method for disposal of this water is to send it.to Radwaste.
The.
concentration of tritium and other nuclides 'exceeds, in this
- sample, the lower limit - of. detection for. tritium, and the "statistically significant" levels of the other huclides.
If contact you `:have questions concerning me at.your earliest convenience. this Iconclusion, please
.4
.3;
MEMORANDUM To Steve Skibniowsky Date: Augst 20, 1992 From Steve McAvoy
-Y-N File: 17.2
Subject:
TB Clean Sump Following the contamination *incident of the*Turbine Building Clean Sump at the 222' level on August 14,'1992, sources of water feeding that sump were checked to Environmental Release limiits for gamma emitters and tritium.
The-following statistically significant radionuclides-were quantified:
Source Nuclide "Activity (uCi/ml)
- Gamma, H-3
<Env. LLD Circ.* Water
- Gamma, H-3
<Env. LLD Station Air:
Compressor Blowdown H-3 1-133 Cs-138 Ba-139 Y-91m Xe-135 5.7 E-5*
1.05 E-8 8 7.53 E-7 5.37 E-7 5.22 E-8 7.89 E-9 Although the dilution factors are. great and would probably result in the'total activity in the sump being below allowable' release limits, the discharge of the Air Compressor Blowdown to the TB *Clean Sump should be discontinued as it would constitute a release of radioactive liquid from the RCA.
19-AUG-92 20:08:15 VERMONT YANKEE NUCLEAR POWER CORPORATION SAMPLE DATE..........
19-AU
- 00:00 SAMPLE IDENTIFICATION:
TYPE OF SAMPLE.......
LIQUID MARINELLI SAMPLE QUANTITY......
1000.000 UNITS:
ML.
SAMPLE-GEOMETRY........
VY2005 OPERATOR...............
KLH EFFICIENCY FILE NAME.:
EFF.VY2005,,
ACQUIRE DATEj 19-AUG-92 14:34:41
- FWHM(1332) 1.897 PRESET TIME(LIVE):
20000. SEC
- SENSITIVITY:
5.000 ELAPSED REAL *TIME:
20000. SEC
- SHAPE PARAMETER': 10.0 %
ELAPSED LIVE TIME:
20000. SEC
- NBR ITERATIONS:
10.
DETECTOR..:
20% HPGE
- LIBRARY NUCL.LIBI CALIB :DATE:
19-AUO-92 00:39:05
- ENERGY TOLERANCE 1.500KV KEV/CHNL..:
.0.5001647
- -HALF LIFE RATIO 8.00 OFFSET....: -0.1161263 KEV
- ABUNDANCE LIMIT 80.00%
Q. COEFF..:
O.OOOE-01 KEV/C**2
- DECAY TIME (MIN) 34.0 ENERGY WINDOW 24.89 TO 2048.56 1.00-SIGMA %ERR BKGND FWHM CHANNEL LEFT PW CTS/SEC %ERR PK IT ENERGY.
1 24 34 5
6 78 10 11 12 13 14 15 16
.17 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
46.39 62.81 93.24 165.97 185.70 238.42 249.84 462.79 510.80 529.46
.546.45
'555.30 583.24 871.41 1009.08 1435.37 1460.02 AREA 155.
111.
249.
506.
92.
33.
79.
141.
205.
67.
40.
52.
24.
30.
85.
127.
23.
PEAK FIT
- 286.
259.
374.
242.
145.
154.
106.
52.
104.
40.
48.
54.
34.
28.
37.
23.
9.
1.01 1.09 1.32 0.96 1.34 0.86 1.30 1.33 2.19 4.34 0.68 0.92 1.29 0.76 1.77 1.49 1.82 92.98 125.82 186.66 332.07 371.52 476.91 499.74 925.51 1021.49 1058.81 1092.76 1110.47 1166.32 1742.47 2017.72 2870.02 2919.32
- 89 121 181 328 368 474 495 922 1014 1052 1087 1108 1163 1736 2009 2865 2916
.10 7.76E-03 9 5.54E-03 14 1.24E-02 10 2.53E-02 8 4.59E-03 8 1.65E-03 9 3.97E-03 9 7.04E-03 16 1.03E-02 14/3.37E-03 12 1.99E-03 9 2.58E-03 7 1.20E-03 10 1.51E-03 14 4.27E-03 13 6.33E-03 7 1.16E-03 22.3 28.7 17.9 7.4 26.0 66.4 27.6 13.1
.13.3 27.8 41.1 30.8 47.1 39.8 16.4 13.4 33.3 SEARCH COMPLETED (REV 15.7) 0
- N3CLIDE IDENTIFICATION SYSTEM (REV JUN 87)
SUMMARY
OF NUCLIDE ACTIVITY TOTAL PEAKS IN SPECTRUM 17 UNIDENTIFLED PEAKS 8
IDENTIFIED IN
SUMMARY
REPORT 9
52.94%
FISSION GAS 1.00-SIGMA NUCLIDE SBHR C.
CI /UNIT ERROR
.175E
-9 PAGE 1
1.00-SIGMA
%ERR 27.57 FISSION NUCLIDE qzq-?
PRODUCT SBHR FP.
- 20. 80H
'49.71M 32.20M 82.71M DECAY 1.117 7.612 15.150 3.979 UC
/UNIT.
1.00-SIGMA ERROR 2.912E -9 1.608E -8 1.009E. -7 3.973E -8 1'00-SIGMA
%ERR 27.80 30.79 13.39 7.40 VERMONT YANKEE QUANTITATIVE RADIOISOTOPIC LLD ANALYSIS 19 AUG 1992 20:11:36 LLD LIMIT INDICATES LLD NOT MET
- NEXT TO NUCLIDE MN-54 FE-59 CO-58 CO-60 ZN-65 ZR-95 NB-95 1-131 CS-134 CS-137 BA-140 LA-140 LLD UCI/ML
- 5. 651E-09
- 9. 619E-09
- 4. 578E-09 5.855E-09
- 1. 191E-08 7.436E-09 5.347E-09 4.580E-09 5.577E-09 4.816E-09
- 1. 605E-08
- 3. OE-08 1.5E-08
- 1. 5E-08
- 3. OE-08
- 1. 5E-08
- 1. 5E-OS
- 1. SE-OS
- 1. SE-0O
- 1. SE-08 1.5E-08
-A( f&eevvt c-t d* <